CN104425045A - Information processing method of loop voltage stabilizer in nuclear power plant and checking method - Google Patents

Information processing method of loop voltage stabilizer in nuclear power plant and checking method Download PDF

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Publication number
CN104425045A
CN104425045A CN201310413734.8A CN201310413734A CN104425045A CN 104425045 A CN104425045 A CN 104425045A CN 201310413734 A CN201310413734 A CN 201310413734A CN 104425045 A CN104425045 A CN 104425045A
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liquid level
pressure release
release case
level rise
case liquid
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CN104425045B (en
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何继强
侯晔
任合斌
陈述清
王保生
荀明磊
陈得胜
蔡亚清
杨敬祥
王亚明
岑相成
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China General Nuclear Power Corp
Daya Bay Nuclear Power Operations and Management Co Ltd
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China General Nuclear Power Corp
Daya Bay Nuclear Power Operations and Management Co Ltd
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin

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  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Examining Or Testing Airtightness (AREA)

Abstract

The application relates to an information processing method of a loop voltage stabilizer in a nuclear power plant and a checking method. The information processing method comprises the following steps: determining a corresponding relation between the liquid-level rising rate of a pressure releasing box and the loop leakage rate according to the structural relation between the liquid-level height during normal operation of the pressure releasing box and the pressure releasing box, and converting the liquid-level rising rate of the current pressure releasing tank into a value with the same unit as the loop leakage rate according to the corresponding relation; and according to the corresponding relation, establishing a matching relation of a processing plan for the liquid-level rising rate of the pressure releasing box and the loop leakage rate. The information processing method and the checking method have the advantages that the liquid-level rising rate is converted into the existing standard loop leakage rate, the problem that no standard exists for liquid-level rise of the pressure releasing box in the nuclear power plant in a long term is solved; by the establishment of the matching relation of the processing plan for the liquid-level rising rate of the pressure releasing box and the loop leakage rate, the problem of no intervention means of the liquid-level rise of the pressure releasing box in the nuclear power plant in a long term is solved, so that unnecessary disassembly and maintenance of valves are reduced and further the exposure dose to workers and radioactive wastes are reduced.

Description

One loop of nuclear power station pressurizer system information processing method and arrange distinguish method
Technical field
The application relates to technical field of nuclear power, particularly relates to a kind ofly to be applicable to pressurized-water reactor nuclear power plant primary Ioops pressurizer system information processing method and the too fast investigation disposal route of a kind of liquid level rise speed being applicable to pressurized-water reactor nuclear power plant primary Ioops voltage stabilizer pressure release case.
Background technology
Nuclear power station (Nuclear Power Plant) is the generating plant that the energy utilizing nuclear fission (Nuclear Fission) or nuclear fusion (Nuclear Fusion) to react to discharge produces electric energy.In principle, nuclear power station achieves the energy conversion of nuclear energy-heat energy-electric energy.From equipment aspect, the reactor of nuclear power station and steam generator serve and are equivalent to the fossil fuel of thermal power station and the effect of boiler.Energy conversion in nuclear power station realizes by means of three loops.Reactor coolant enters reactor under the driving of main pump, and the outlet from reactor vessel after flowing through reactor core flows out, and enters steam generator, then gets back to main pump, the circulation process (being also called primary Ioops) of Here it is reactor coolant.Circulating in process, reactor coolant takes away the heat of nuclear reaction generation from reactor core, and in a vapor generator, transfers heat to the water of secondary circuit under the condition of entity isolation.Secondary circuit water is heated, and the steam of generation removes driving steam turbine again, drives the electrical power generators coaxial with steam turbine.Weary steam after acting is condensed into water by seawater or river, lake-water cooling water (three Loop Waters), then adds in steam generator within the condenser.To take seawater as the effect in three loops of medium be weary steam-condensation is water, and that takes away power station abandons heat simultaneously.
One loop of nuclear power station system is a loop, therefore, when the cooling medium generation temperature variation in system causes volume fluctuations, system pressure certainly will be caused to produce corresponding change.If system pressure increases to over design pressure, system and damage of facilities will be caused; If pressure drop is too low, reactor core local boiling or bulk boiling can be caused again, cause reactor core to burn, thus cause serious safety problem.Therefore in order to nuclear plant safety reliably runs, must carry out control and protection to the pressure of reactor-loop system, Here it is sets up the object of pressure relief system, and voltage stabilizer is then the major equipment of pressure relief system.
The Main Function of voltage stabilizer maintains on setting valve by the pressure of primary Ioops, vaporizes in primary Ioops to prevent coolant water.When the pressure of voltage stabilizer exceedes the setting valve of safety valve, safety valve is opened, and is drained into rapidly in release case by the steam in voltage stabilizer, makes voltage stabilizer release, play overpressure protection effect.
The major function of voltage stabilizer blowdown valve be collect, positive steam that condensation and cooling pressurizer safety valve, residual heat removal system (RRA) safety valve, chemistry and volume system (RCV) safety valve discharge and the cooling medium that primary Ioops system valve rod filler device leaks.Pressure release case makes the cooling medium of primary Ioops not to containment vessel discharge, avoids with active primary Ioops fluid the pollution of containment.
Under normal circumstances, voltage stabilizer pressure release case liquid level rise speed should be almost constant, close to fixed value.But find through on-the-spot actual observation, the very fast problem of voltage stabilizer pressure release case liquid level rise speed repeatedly occurs repeatedly.But, because current nuclear power station does not have primary Ioops voltage stabilizer pressure release case liquid level rise standard limit, do not go up for pressure release case liquid level yet and intervention means is provided, cause this problem to bring puzzlement greatly to nuclear power station staff and be repeatedly subject to nuclear safety office and pay close attention to.And, through the feedback of Institute of Nuclear Power Operation of the U.S. (INPO), once there is voltage stabilizer shower valve packing together and leaked in U.S.'s nuclear power station, primary Ioops system leak reactor is caused promptly to stop the event of pen, and the leakage of voltage stabilizer shower valve packing is recycled to voltage stabilizer pressure release case, thus pressure release case liquid level is caused to go up.That when each overhaul, strip inspection primary Ioops valve, adds additional the radioactive dose of nuclear power station staff, creates a large amount of radioactive waste simultaneously, and adds financial cost for the common way that pressure release case liquid level rise speed is too fast at present.
Summary of the invention
The application provides a kind of and is applicable to pressurized-water reactor nuclear power plant primary Ioops pressurizer system information processing method and the too fast investigation disposal route of a kind of liquid level rise speed being applicable to pressurized-water reactor nuclear power plant primary Ioops voltage stabilizer pressure release case, goes up without standard, problem without intervention means in order to solve current one loop of nuclear power station voltage stabilizer pressure release case liquid level.
According to the first aspect of the application, the application provides a kind of one loop of nuclear power station pressurizer system information processing method, comprising: corresponding determining step, according to the liquid level of pressure release case normal operation period and the structural relation of pressure release case; Obtaining step, obtains current pressure release case liquid level rise speed; Scaling step, determines the corresponding relation of pressure release case liquid level rise speed and primary Ioops slip, is the numerical value identical with the unit of primary Ioops slip according to described corresponding relation by current pressure release case liquid level rise rate transition; Coupling establishment step, according to the alignment processing prediction scheme of described primary Ioops slip, sets up the matching relationship of pressure release case liquid level rise speed and primary Ioops slip process prediction scheme.The primary Ioops slip of the method by by voltage stabilizer pressure release case liquid level rise rate transition being existing standard, the voltage stabilizer pressure release case liquid level solving the medium-term and long-term existence of current nuclear power station goes up without typical problem.
Further, described scaling step comprises: calculate the per unit slip that per unit liquid level is corresponding, according to result of calculation and historical defect data, determines the corresponding relation of pressure release case liquid level rise speed and primary Ioops slip; According to the reading of the liquid level gauge be connected with described pressure release case, calculate the slip corresponding with current pressure release case liquid level rise speed, described slip is the numerical value identical with the unit of primary Ioops slip.
Further, the shape of described pressure release case is middle for cylindrical and both sides are the spherical crown that volume is identical, the liquid level of described normal operation period is 2 meters to 2.2 meters, the described per unit slip calculating per unit liquid level corresponding comprises: calculate respectively liquid level be 2 meters and 2.2 meters time liquid surface volume, again according to ball-crown body sum cylinder volume formula, calculate liquid level often go up 1 millimeter time volume rate of change, thus obtain corresponding primary Ioops slip.Because the shape of general one loop of nuclear power station voltage stabilizer pressure release case, size and built-in pipeline etc. thereof are standard configuration, per unit slip corresponding to the per unit liquid level calculated accordingly is also fixing usually, therefore, primary Ioops slip corresponding to pressure release case current level rise speed can be calculated easily according to the reading of liquid level gauge, make nuclear power station operator can make corresponding reaction according to this result of calculation soon.
Further, the determining step of the corresponding relation of described pressure release case liquid level rise speed and primary Ioops slip comprises: if pressure release case liquid level rise speed is for being less than first rate designated value, then determine that the primary Ioops slip of its correspondence is for being less than the first leakage designated value; If pressure release case liquid level rise speed is for being more than or equal to first rate designated value and being less than the second speed designated value, then determine that the primary Ioops slip of its correspondence is for being more than or equal to the first leakage designated value; If pressure release case liquid level rise speed is for being more than or equal to the second speed designated value, then determine that the primary Ioops slip of its correspondence is for being more than or equal to the second leakage designated value; Described first rate designated value and the second speed designated value set according to historical defect data, described first leakage designated value is the numerical value calculated according to described scaling step and in conjunction with described first rate designated value, and described second leakage designated value is the numerical value calculated according to described scaling step and in conjunction with described second speed designated value.
Further, described first leaks primary Ioops slip process prediction scheme corresponding to designated value comprises: according to the frequency monitoring pressure release case liquid level rise situation of normal monitoring nuclear power station, or monitoring pressure release case liquid level rise situation follow the tracks of the trend that pressure release case liquid level goes up; The described second primary Ioops slip process prediction scheme of leaking designated value corresponding comprises: determine that pressure release case liquid level goes up and occur extremely, checking and determining pressure release case liquid level rise reason.This embodiment passes through the relevant running technology specification of historical defect data and primary Ioops slip, can learn that the liquid level rise speed of one loop of nuclear power station voltage stabilizer pressure release case belongs to normal monitoring range when what value, the relevant running technology specification of the primary Ioops slip that the liquid level rise speed that therefore can read according to liquid level gauge is corresponding, determine whether monitoring as usual or strengthen monitoring, and judging pressure release case liquid level goes up whether occur exception.
Preferably, described first rate designated value is 10 millimeters of every days, and described first leakage designated value is 6.25 liter per hour, and described second speed designated value is 15 millimeters of every days, and described second leakage designated value is 9.375 liter per hour.
According to the second aspect of the application, the investigation disposal route that the application provides a kind of one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed too fast, comprise: establishment step, according to the corresponding relation of pressure release case liquid level rise speed and primary Ioops slip, be the numerical value identical with the unit of primary Ioops slip by current pressure release case liquid level rise rate transition, and set up the matching relationship of pressure release case liquid level rise speed and primary Ioops slip process prediction scheme; Select step, according to numerical value, in described matching relationship, select corresponding primary Ioops slip process prediction scheme; Investigation step, performs the primary Ioops slip process prediction scheme selected, and when determining that the rise of pressure release case liquid level occurs abnormal, checking and determining pressure release case liquid level rise reason.The liquid level rise speed of the method by foundation and the matching relationship of primary Ioops slip process prediction scheme, make just can learn after obtaining liquid level rise speed and process prediction scheme accordingly, the voltage stabilizer pressure release case liquid level solving the medium-term and long-term existence of current nuclear power station goes up without the problem of intervention means.
In a kind of embodiment of the application, described inspection also determines that pressure release case liquid level rise reason comprises: perform safety valve jumping up pressure fixed value checking and tightness test, if School Affairs test findings is defective, then determine that pressure release case liquid level rise reason is the spring safety valve appearance interior leakage phenomenon of chemical volume control system.Whether this embodiment is cause due to the spring safety valve appearance interior leakage phenomenon of chemical volume control system by safety valve testing determination liquid level rise reason.
In a kind of embodiment of the application, described inspection also determines that pressure release case liquid level rise reason comprises: the pilot operated safety valve bleeder line temperature checking chemical volume control system, judge whether the trend of its temperature occurs rise phenomenon, if there is rise, then determine that pressure release case liquid level rise reason is the pilot operated safety valve appearance interior leakage phenomenon of chemical volume control system.By temperature inspection, this embodiment determines whether liquid level rise reason is cause due to the pilot operated safety valve appearance interior leakage phenomenon of chemical volume control system.
In a kind of embodiment of the application, described inspection also determines that pressure release case liquid level rise reason comprises: the pilot operated safety valve bleeder line temperature checking reactor RHR system, judge whether the trend of its temperature occurs rise phenomenon, if there is rise, then determine that pressure release case liquid level rise reason is the pilot operated safety valve appearance interior leakage phenomenon of reactor RHR system.By temperature inspection, this embodiment determines whether liquid level rise reason is cause due to the pilot operated safety valve appearance interior leakage phenomenon of reactor RHR system.
In a kind of embodiment of the application, described inspection also determines that pressure release case liquid level rise reason comprises: the pilot operated safety valve bleeder line temperature checking reactor coolant loop, judge whether the trend of its temperature occurs rise phenomenon, if there is rise, then determine that pressure release case liquid level rise reason is the pilot operated safety valve appearance interior leakage phenomenon of reactor coolant loop.By temperature inspection, this embodiment determines whether liquid level rise reason is cause due to the pilot operated safety valve appearance interior leakage phenomenon of reactor RHR system.
In a kind of embodiment of the application, described inspection also determines that pressure release case liquid level rise reason comprises: perform loose joint inspection to the packing of the shower valve of reactor coolant loop, reveal if there is packing, then determine that pressure release case liquid level rise reason is the packing leakage of the shower valve of reactor coolant loop; Loose joint inspection is performed to the packing of the isolation valve of reactor coolant loop, reveals if there is packing, then determine that pressure release case liquid level rise reason is the packing leakage of the isolation valve of reactor coolant loop.This embodiment is by determining to packing loose joint inspection whether liquid level rise reason is because the shower valve of reactor coolant loop and/or the packing of isolation valve leak and cause.
In a kind of embodiment of the application, described inspection also determines that pressure release case liquid level rise reason comprises: judge whether reactor boron and water make-up system pressure release case liquid level during opening and closing goes up, go up if there is liquid level, then determine that pressure release case liquid level rise reason is the spray isolation valve appearance interior leakage phenomenon of pressure release case.By the operation opening and closing make-up system, this embodiment determines whether liquid level rise reason is cause due to the spray isolation valve appearance interior leakage phenomenon of pressure release case.
In a kind of embodiment of the application, described inspection also determines that pressure release case liquid level rise reason comprises: the interim operating instruction performing isolation cooling water system cooling coil, rise speed before contrasting pressure release case liquid level rise speed and implement during implementing interim operating instruction, if change appears in liquid level rise speed before and after implementing, then determine that pressure release case liquid level rise reason is that cooling water system cooling coil leaks.By the operation performing interim operating instruction, this embodiment determines whether liquid level rise reason is cause because cooling water system cooling coil leaks.
Further, described pressure release case liquid level rise speed comprises with the determination of the corresponding relation of primary Ioops slip: calculate the per unit slip that per unit liquid level is corresponding, according to result of calculation and historical defect data, determine the corresponding relation of pressure release case liquid level rise speed and primary Ioops slip, described corresponding relation comprises: if pressure release case liquid level rise speed is for being less than first rate designated value, then the primary Ioops slip of its correspondence is for being less than the first leakage designated value, if pressure release case liquid level rise speed is for being more than or equal to first rate designated value and being less than the second speed designated value, then the primary Ioops slip of its correspondence is for being more than or equal to the first leakage designated value, if pressure release case liquid level rise speed is for being more than or equal to the second speed designated value, then the primary Ioops slip of its correspondence is for being more than or equal to the second leakage designated value, wherein said first rate designated value and the second speed designated value set according to historical defect data, described first leakage designated value is the numerical value calculated according to described scaling step and in conjunction with described first rate designated value, described second leakage designated value is the numerical value calculated according to described scaling step and in conjunction with described second speed designated value, according to the reading of the liquid level gauge be connected with described pressure release case, calculate the slip corresponding with current pressure release case liquid level rise speed, described slip is the numerical value identical with the unit of primary Ioops slip.
Further, described first leaks primary Ioops slip process prediction scheme corresponding to designated value comprises: according to the frequency monitoring pressure release case liquid level rise situation of normal monitoring nuclear power station, or monitoring pressure release case liquid level rise situation follow the tracks of the trend that pressure release case liquid level goes up; The described second primary Ioops slip process prediction scheme of leaking designated value corresponding comprises: determine that pressure release case liquid level goes up and occur extremely, checking and determining pressure release case liquid level rise reason.This embodiment passes through the relevant running technology specification of historical defect data and primary Ioops slip, can learn that the liquid level rise speed of one loop of nuclear power station voltage stabilizer pressure release case belongs to normal monitoring range when what value, the relevant running technology specification of the primary Ioops slip that the liquid level rise speed that therefore can read according to liquid level gauge is corresponding, determine whether monitoring as usual or strengthen monitoring, and judging pressure release case liquid level goes up whether occur exception.
The beneficial effect of the application is: by by voltage stabilizer pressure release case liquid level rise rate transition being the primary Ioops slip of existing standard, the voltage stabilizer pressure release case liquid level solving the medium-term and long-term existence of current nuclear power station goes up without typical problem, by the liquid level rise speed of foundation and the matching relationship of primary Ioops slip process prediction scheme, make just can learn after obtaining liquid level rise speed and process prediction scheme accordingly, the voltage stabilizer pressure release case liquid level solving the medium-term and long-term existence of current nuclear power station goes up without the problem of intervention means, thus decrease unnecessary valve Disintegration overhaul, and then decrease radioactive dose and the radioactive waste of nuclear power station staff.
Accompanying drawing explanation
Fig. 1 is the one loop of nuclear power station pressurizer system information processing method schematic flow sheet of a kind of embodiment of the application;
Fig. 2 is primary Ioops voltage stabilizer pressure release case and annexation schematic diagram thereof;
Fig. 3 is the one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed of a kind of embodiment of the application and primary Ioops slip and the corresponding relation schematic diagram processing prediction scheme thereof;
Fig. 4 is the schematic flow sheet of the too fast investigation disposal route of the one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed of a kind of embodiment of the application;
Fig. 5 is the too fast rear basic reason investigation process schematic diagram of the one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed of a kind of embodiment of the application;
Fig. 6 to Fig. 8 is voltage stabilizer pressure release case driven dimension schematic diagram in a kind of embodiment of the application, and wherein Fig. 6 is the appearance schematic diagram of pressure release case, and Fig. 7 is the side schematic view of the profile of pressure release case, and Fig. 8 is the diagrammatic cross-section of profile from A-A direction of pressure release case.
Embodiment
The mentality of designing of itself asking is that voltage stabilizer pressure release case liquid level rise speed is scaled primary Ioops slip, formulate rational pressure release case liquid level rise limit value, analyse in depth based on the workflow of pressure release case simultaneously, the too fast reason investigation of a kind of comprehensive, concrete, exercisable voltage stabilizer pressure release case liquid level rise speed and disposal route are provided, make can perform relevant prediction scheme when liquid level goes up and exceedes limit value.
By reference to the accompanying drawings the present invention is described in further detail below by embodiment.
Embodiment 1:
As shown in Figure 1, the present embodiment provides the disposal route of a kind of one loop of nuclear power station pressurizer system information especially pressure release case liquid level information, comprises the following steps S101 ~ S103:
Corresponding determining step S101, according to the liquid level of pressure release case normal operation period and the structural relation of pressure release case, determines the corresponding relation of pressure release case liquid level rise speed and primary Ioops slip;
Obtaining step S102, obtains current pressure release case liquid level rise speed;
Current pressure release case liquid level rise rate transition is the numerical value identical with the unit of primary Ioops slip according to this corresponding relation by scaling step S103;
Coupling step S104, according to the alignment processing prediction scheme of primary Ioops slip, sets up the matching relationship of pressure release case liquid level rise speed and primary Ioops slip process prediction scheme.
Particularly, for being primary Ioops slip by voltage stabilizer pressure release case liquid level rise rate transition, the function and structure feature first understanding primary Ioops slip and voltage stabilizer pressure release case is needed.
One loop of nuclear power station slip is defined as in the unit interval by the cooling medium total amount F of primary Ioops system pressure boundary leaking to secondary circuit or other system p, it can be divided into again quantitative slip (confirmable leakage) F qwith non-quantitation slip (not confirmable leakage) F nqtwo parts.Wherein, quantitative slip F qrefer to that certain consideration in the design determines the leakage of position, they are collected into the container of specifying, and flow can measure.Non-quantitation leaks F nqrefer to the leakage in other situation that above-mentioned definition do not comprise, this is that uncertain or position, a kind of position is determined but the immeasurablel leakage of leakage flow.
Due to the needs of radioactive shield, nuclear power station has strict limit value to primary Ioops slip.Obviously, the limit value that non-quantitation leaks is wanted strict, as certain nuclear power station unit operation Technical specification just regulation, non-quantitation slip F nqbe greater than 230L/h or total slip F pwhen being greater than 2300L/h, all needing at the appointed time unit to be imported and correspondingly move back anti-state.Conveniently, only F need be carried out in nuclear power station day-to-day operation technical manual nqcalculate, namely primary Ioops and the total slip of border non-quantitation thereof must be less than 230L/h.
For voltage stabilizer pressure release case, under Operation at full power operating mode, pressure release case can receive the steam of the voltage stabilizer vapor space of 110%, namely within the time that pressurizer safety valve opens 30 seconds, pressure release case approximately can receive 1.7 tons of steam, in pressure release case pressure release case, pressure is no more than 45bar.a in the case, and temperature is no more than 93 DEG C.But the limited volume of pressure release case, it can not accept the steam that pressurizer safety valve successively discharges.
As shown in Figure 2, common pressure release case is a Horizontal cylinder shape low pressure vessel, and its two ends, left and right are hemispherical head, and total measurement (volume) is about 37m 3, under normal circumstances, in case, water level is 65% of overall height, and water temperature maintains 40 DEG C.Top is filled with nitrogen, and rated pressure is 1.2bar.a(absolute pressure value).The object of inflated with nitrogen is that the oxygen mix in the hydrogen and air contained in the steam preventing from being discharged by voltage stabilizer produces detonation gas.Regularly from hydrogen and the oxygen concentration of sample analysis gathering in case, and be discharged into nuclear island draining and draining system (PRE).
The shower that pressure release case is supplied water by reactor boron and water make-up system (REA) built with one, a hydrophobic pipeline connecing RPE system, the former is used for cooling pressure release case when safety valve discharges, and the latter is used for the draining when cistern water level height.Have a cooling coil supplied water by component cooling water system (RRI) in the hydrospace of case, near bottom, a bubbling pipe is being housed in the axial direction, this root pipe is connected with voltage stabilizer blowdown line.Pressure release upper box part is provided with two rupture disks in case stopping leak pressure case superpressure, and the emission of rupture disk enters in the air of containment, and its relieving capacity equals voltage stabilizer three safety valve discharge capacity sums.
During normal operation, the water in pressure release case is cooled incessantly by the RRI system equipment chilled water flow through in coiled pipe in case.If water temperature more than 60 DEG C, then sends alerting signal, operator wants manually opened voltage stabilizer pressure release case spray isolation valve, and the desalination degassed water from REA system is sprayed into through shower and cools pressure release case, maximum spray flux is 13.6m 3/ h.If water level is too high, then open drain valve bottom pressure release case to RPE System drainage, but water temperature high to 65 DEG C time, automatically forbid that the drain valve bottom pressure release case is opened, flow to RPE system to avoid high-temperature water.
By the structure analysis to voltage stabilizer pressure release case, normal operation period pressure release case liquid level is at 2.0 ~ 2.2m, as calculated spherical crown and columnar volume known, every millimeter of corresponding slip of liquid level is 14.414 to 15.678 liters, and due to nuclear plant safety require very high, therefore this calculating does not consider that cooling coil volume affects, too conservative.What be specifically related to here is calculated as follows:
As shown in Figure 6 to 8, voltage stabilizer pressure release case is made up of the identical spherical crown of two Side Volumes and mediate cylindrical tank body, and wherein, left side spherical crown volume is set to V 2, right side spherical crown volume is set to V 3, mediate cylindrical volume is set to V 1for left side spherical crown, if the radius of spherical crown is r, the line segment that intersection point between spherical crown and right cylinder to the centre of sphere is formed and horizontal direction shape into θ angle, spherical crown and cylindrical maximum distance are a, and the distance between the corresponding intersection point on spherical crown of this maximum distance and the intersection point between spherical crown and right cylinder is r i, suppose cylindrical height L, the diameter of round sides is D, also supposes that cylindrical area is S on A-A section simultaneously 1, left side spherical corona's area is S 2, right side spherical corona's area is S 3, in this section, cylindrical width is D i.Normal operation period pressure release case liquid level is at 2.0 ~ 2.2m, and when calculating jar liquid level rise speed, the change of the sectional area that every 1mm goes up can be ignored.Therefore calculate liquid level liquid surface area when being 2.0m and 2.2m respectively, the rate of change of the every rise 1mm volume of liquid level can be drawn, thus calculate liquid level rise speed.
When pressure release case liquid level is h, computation process is as follows:
S 1 = L · D i = L · 2 ( D 2 ) 2 - ( h - D 2 ) 2 = L · 2 hD - h 2 - - - ( 1 )
By r 2 - ( r - a ) 2 = ( D 2 ) 2 , Can draw
r = D 2 + 4 a 2 8 a - - - ( 2 )
By r i r = D 2 - h D 2 , Can draw
r i = D - 2 h D r = D - 2 h D · D 2 + 4 a 2 8 a - - - ( 3 )
Because both sides spherical crown volume is identical, can draw
s 2 = s 3 = π r i 2 arcsin D i 2 r i 360 - D 2 r i cos ( arcsin D i 2 r i ) - - - ( 4 )
When liquid level is h, namely have
S = S 1 + S 2 + S 3 = 2 L hD - h 2 + 2 [ π r i 2 arcsin D i 2 r i 360 - D 2 r i cos ( arcsin D i 2 r i ) ] - - - ( 5 )
D i = D 2 4 - ( h - D 2 ) 2 = Dh - h 2 - - - ( 6 )
From Fig. 6-8, L=60+1220+1220+1960+60=4520mm=4.52m, D=3000mm=3m, a=856-60=796mm=0.796m.
1) as h=2.0m, data are substituted into formula (3), (5), (6), then calculates S 1=15.678m 2, namely now liquid level often goes up 1mm, and volume increases V 1=15.678L;
2) as h=2.2m, data are substituted into formula 3,5,6, then calculates S 2=14.414m 2, namely now liquid level often goes up 1mm, and volume increases V 2=14.414L.
Accordingly, voltage stabilizer pressure release case current level rise speed can be scaled primary Ioops slip, that is, according to the reading of the liquid level gauge be connected with pressure release case, learn that rise speed is K millimeter every day (mm/d), then corresponding primary Ioops slip F currentfor following formula:
F current=K × (14.414 ~ 15.678)/24, unit: liter per hour (L/h) (7)
Thus the corresponding relation of pressure release case liquid level rise speed and primary Ioops slip can be defined as:
If pressure release case liquid level rise speed is for being less than first rate designated value, then the primary Ioops slip of its correspondence is for being less than the first leakage designated value;
If pressure release case liquid level rise speed is for being more than or equal to first rate designated value and being less than the second speed designated value, then the primary Ioops slip of its correspondence is for being more than or equal to the first leakage designated value;
If pressure release case liquid level rise speed is for being more than or equal to the second speed designated value, then the primary Ioops slip of its correspondence is for being more than or equal to the second leakage designated value;
Wherein, first rate designated value and the second speed designated value set according to historical defect data, and the source of historical defect data can be, the data of such as collecting when nuclear power station overhaul, or the data of collecting during nuclear power station day-to-day operation.First leakage designated value is the numerical value calculated according to formula (7) and in conjunction with first rate designated value, and the second leakage designated value is the numerical value calculated according to formula (7) and in conjunction with the second speed designated value.
In practice, according to the historical defect data of record, multiple one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed repeatedly reaches about 10mm/d, and being scaled primary Ioops slip is 6.25L/h, and distance primary Ioops slip standard (i.e. aforesaid 230L/h) is far away.And pressure release case liquid level rise speed will cause voltage stabilizer endless tube hydrogen richness to rise after increasing, and according to historical experience, liquid level rise speed is when about 10mm/d, and the annual voltage stabilizer endless tube nitrogen purging that performs is not more than 1 time, belongs in tolerance interval; In addition, about nuclear power station alarm card requires that primary Ioops voltage stabilizer pressure release case liquid level to reach after alarming value 2.42 meters draining to 2 meter, drain height 0.42 meter, if calculate by slip 10mm/d, draining frequency is 42 days, also belongs in tolerance interval.And primary Ioops voltage stabilizer pressure release case liquid level rise speed reaches and is greater than 10mm/d and to be less than the situation of 15mm/d less in historical experience, need start to strengthen paying close attention to and following the tracks of trend; Learn according to historical experience, multiple one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed is about 15mm/d to the maximum.Therefore, first rate designated value can be set to 10mm/d, it is 6.25L/h that first of its correspondence leaks designated value, and the second speed designated value is 15mm/d, and the second leakage designated value is 9.375L/h.
Syncaryon power station running technology specification, primary Ioops voltage stabilizer pressure release case liquid level rise speed control criterion can be drawn, namely the relation gone up between speed-primary Ioops slip-process prediction scheme, particularly, when primary Ioops slip is for being less than 6.25L/h, according to the frequency monitoring pressure release case liquid level rise situation of normal monitoring nuclear power station; When primary Ioops slip is for being more than or equal to 6.25L/h and being less than 9.375L/h, strengthen monitoring pressure release case liquid level rise situation and the trend of following the tracks of the rise of pressure release case liquid level; When primary Ioops slip is for being more than or equal to 9.375L/h, then determines that pressure release case liquid level goes up and occur extremely, checking and determining pressure release case liquid level rise reason, relevant prediction scheme can be started and process.For understanding directly perceived, can with reference to the form shown in figure 3.
The primary Ioops slip of the present embodiment by by voltage stabilizer pressure release case liquid level rise rate transition being existing standard, the voltage stabilizer pressure release case liquid level solving the medium-term and long-term existence of current nuclear power station goes up without typical problem, by the liquid level rise speed of foundation and the matching relationship of primary Ioops slip process prediction scheme, operator makes just can learn after obtaining liquid level rise speed and processes prediction scheme accordingly, so that can adopt to the one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed obtained process prediction scheme accordingly.
Embodiment 2:
As shown in Figure 4, the investigation disposal route that the present embodiment provides a kind of one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed too fast, comprising:
Establishment step S401, according to the corresponding relation of pressure release case liquid level rise speed and primary Ioops slip, be the numerical value identical with the unit of primary Ioops slip by current pressure release case liquid level rise rate transition, and set up the matching relationship of pressure release case liquid level rise speed and primary Ioops slip process prediction scheme;
Select step S403, according to numerical value, in this matching relationship, select corresponding primary Ioops slip process prediction scheme;
Investigation step S405, performs the primary Ioops slip process prediction scheme selected, and when determining that the rise of pressure release case liquid level occurs abnormal, checking and determining pressure release case liquid level rise reason.
Wherein the specific implementation process of step S401 and S403 can the associated description of reference example 1, no longer repeats.The following specifically describes step S405.
As shown in Figure 2, the water source collected by voltage stabilizer pressure release case has four, respectively:
1. RCP/RCV/RRA security of system valve water;
2. RCP valve packing draws leakage water;
3. REA shower water;
4. RRI cooling coil water.
According to each road water, for certain nuclear power station No. 1 unit L1, and carry out coherence check from specialized department's cooperation:
For 1. RCP/RCV/RRA security of system valve water, it comprises the water leakage of RCP system pilot operated safety valve (such as RCP020/021/022VP), RCV system pilot operated safety valve (such as RCV201VP), RRA system pilot operated safety valve (such as RRA018/115VP) and RCV system spring safety valve (such as RCV252VP).Be widely used in the SEBIM safety valve that the pilot operated safety valve on nuclear power station important system equipment provides for French SEBIM company at present; it is for pressure vessel and pressure-bearing pipeline provide overpressure protection; there is the advantage that common safety valve is incomparable; not only sealing is tight, precision of adjusting is high for the design of its special pilot control, be swift in motion; and well solve the significant trouble hidden danger of not returning seat after conventional security valve is opened, be the important leverage of nuclear power generating sets safe and stable operation.
Thus, for 1. RCP/RCV/RRA security of system valve water, determine pressure release case liquid level rise reason by checking as follows:
I. perform safety valve jumping up pressure fixed value checking and tightness test, if School Affairs test findings is defective, then determine that pressure release case liquid level rise reason is the spring safety valve appearance interior leakage phenomenon of RCV system, this investigation action adopts when overhaul usually;
II. the pilot operated safety valve bleeder line temperature of RCV system is checked, judge whether the trend of its temperature occurs rise phenomenon, if there is rise, then determine that pressure release case liquid level rise reason is the pilot operated safety valve appearance interior leakage phenomenon of RCV system, this investigation action adopts when current check usually;
III. the pilot operated safety valve bleeder line temperature of RRA system is checked, judge whether the trend of its temperature occurs rise phenomenon, if there is rise, then determine that pressure release case liquid level rise reason is the pilot operated safety valve appearance interior leakage phenomenon of RRA system, this investigation action adopts when current check usually;
IV. the pilot operated safety valve bleeder line temperature of RCP system is checked, judge whether the trend of its temperature occurs rise phenomenon, if there is rise, then determine that pressure release case liquid level rise reason is the pilot operated safety valve appearance interior leakage phenomenon of RCP system, this investigation action adopts when current check usually.
Draw leakage water for 2. RCP valve packing, it packing comprising RCP stabilizator shower valve (such as RCP001/002VP) and isolation valve (such as RCP102/103/202/203/302/303VP) draws and leaks.
Thus, leakage water being drawn for 2. RCP valve packing, determining pressure release case liquid level rise reason by checking as follows:
I. loose joint inspection is performed to the packing of the shower valve of RCP system; namely open packing draw leak loose joint checked whether packing leak vestige, boron crystallization etc.; if existed, then determine that pressure release case liquid level rise reason is the packing leakage of the shower valve of RCP system, this investigation action adopts when overhaul usually;
II. loose joint inspection is performed to the packing of the isolation valve of RCP system, namely open packing draw leak loose joint checked whether packing leak vestige, boron crystallization etc., if existed, then determine that pressure release case liquid level rise reason is the packing leakage of the isolation valve of RCP system, this investigation action adopts when overhaul usually.
For 3. REA shower water, it is leaked by voltage stabilizer and supplies water to spray isolation valve (such as REA001/002PO).
Thus, for 3. REA shower water, determine pressure release case liquid level rise reason by checking as follows:
Judge whether REA system pressure release case liquid level during opening and closing goes up, go up if there is liquid level, then determine that pressure release case liquid level rise reason is the spray isolation valve appearance interior leakage phenomenon of pressure release case, this investigation action adopts when current check usually.
For 4. RRI cooling coil water, it is because corrosive pipeline perforation leakage causes water.
Thus, for 4. RRI cooling coil water, determine pressure release case liquid level rise reason by checking as follows:
Perform the interim operating instruction (TOI) of RRI system cools coil pipe, rise speed before contrasting pressure release case liquid level rise speed and implement during implementing interim operating instruction, if before and after implementing there is change in liquid level rise speed, then determine that pressure release case liquid level rise reason is that RRI system cools coil pipe leaks, this investigation action adopts when current check usually.
The processing scheme after basic reason that one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed exceeds standard, the action of reason investigation and investigation can be determined from above-mentioned analysis, namely the very fast question processing method of liquid level rise speed can be verified respectively for aforementioned four tunnel waters and check, as shown in Figure 5.
The primary Ioops slip of the present embodiment by by voltage stabilizer pressure release case liquid level rise rate transition being existing standard, the voltage stabilizer pressure release case liquid level solving the medium-term and long-term existence of current nuclear power station goes up without typical problem, by the liquid level rise speed of foundation and the matching relationship of primary Ioops slip process prediction scheme, make just can learn after obtaining liquid level rise speed and process prediction scheme accordingly, and can check when rise speed is too fast and determine liquid level rise reason, thus corresponding disposal route can be adopted to deal with problems according to the reason investigated out, the voltage stabilizer pressure release case liquid level that visible the present embodiment solves the medium-term and long-term existence of current nuclear power station goes up without the problem of intervention means, thus decrease unnecessary valve Disintegration overhaul, and then decrease radioactive dose and the radioactive waste of nuclear power station staff.
To sum up embodiment, known itself please by 1) quantitative test and 2 of relation between pressure release case water level rise speed and primary Ioops slip) pressure release case water level goes up possible source analysis, namely RCP/RCV/RRA security of system valve water, RCP valve packing draw leakage water, REA shower water, RRI cooling coil water, formulated pressure release case water level rise speed control criterion and rise speed exceed standard after basic reason investigation and process prediction scheme, that is:, during rise speed <10mm/d, monitor according to normal frequency; Rise speed >=10mm/d and≤15mm/d, strengthen monitoring and following the tracks of trend; Rise speed >=15mm/d, start-up check prediction scheme.Thus the voltage stabilizer pressure release case water level solving the medium-term and long-term existence of nuclear power station goes up without standard, significant problem without intervention means, decrease unnecessary valve Disintegration overhaul, and decrease radioactive dose and the radioactive waste of staff, there is important economic and social benefit.
Above content is the further description done the application in conjunction with concrete embodiment, can not assert that the concrete enforcement of the application is confined to these explanations.For the application person of an ordinary skill in the technical field, under the prerequisite not departing from the application's design, some simple deduction or replace can also be made.

Claims (16)

1. an one loop of nuclear power station pressurizer system information processing method, is characterized in that, comprising:
Corresponding determining step, according to the liquid level of pressure release case normal operation period and the structural relation of pressure release case, determines the corresponding relation of pressure release case liquid level rise speed and primary Ioops slip;
Obtaining step, obtains current pressure release case liquid level rise speed;
Current pressure release case liquid level rise rate transition is the numerical value identical with the unit of primary Ioops slip according to described corresponding relation by scaling step;
Coupling establishment step, according to the alignment processing prediction scheme of described primary Ioops slip, sets up the matching relationship of pressure release case liquid level rise speed and primary Ioops slip process prediction scheme.
2. one loop of nuclear power station pressurizer system information processing method as claimed in claim 1, is characterized in that,
Described corresponding determining step comprises: calculate the per unit slip that per unit liquid level is corresponding, according to result of calculation and historical defect data, determines the corresponding relation of pressure release case liquid level rise speed and primary Ioops slip;
Described obtaining step comprises: according to the reading of the liquid level gauge be connected with described pressure release case, obtains current pressure release case liquid level rise speed;
Described scaling step comprises: calculate the slip corresponding with current pressure release case liquid level rise speed, described slip is the numerical value identical with the unit of primary Ioops slip.
3. one loop of nuclear power station pressurizer system information processing method as claimed in claim 2, it is characterized in that, the shape of described pressure release case is middle for cylindrical and both sides are the spherical crown that volume is identical, the liquid level of described normal operation period is 2 meters to 2.2 meters, the described per unit slip calculating per unit liquid level corresponding comprises: calculate respectively liquid level be 2 meters and 2.2 meters time liquid surface volume, again according to ball-crown body sum cylinder volume formula, calculate liquid level often go up 1 millimeter time volume rate of change, thus obtain corresponding primary Ioops slip.
4. one loop of nuclear power station pressurizer system information processing method as claimed in claim 2, it is characterized in that, the determining step of the corresponding relation of described pressure release case liquid level rise speed and primary Ioops slip comprises:
If pressure release case liquid level rise speed is for being less than first rate designated value, then determine that the primary Ioops slip of its correspondence is for being less than the first leakage designated value;
If pressure release case liquid level rise speed is for being more than or equal to first rate designated value and being less than the second speed designated value, then determine that the primary Ioops slip of its correspondence is for being more than or equal to the first leakage designated value;
If pressure release case liquid level rise speed is for being more than or equal to the second speed designated value, then determine that the primary Ioops slip of its correspondence is for being more than or equal to the second leakage designated value;
Described first rate designated value and the second speed designated value set according to historical defect data, described first leakage designated value is the numerical value calculated according to described scaling step and in conjunction with described first rate designated value, and described second leakage designated value is the numerical value calculated according to described scaling step and in conjunction with described second speed designated value.
5. one loop of nuclear power station pressurizer system information processing method as claimed in claim 4, it is characterized in that, described first rate designated value is 10 millimeters of every days, described first leakage designated value is 6.25 liter per hour, described second speed designated value is 15 millimeters of every days, and described second leakage designated value is 9.375 liter per hour.
6. one loop of nuclear power station pressurizer system information processing method as claimed in claim 4, is characterized in that,
Described first leaks primary Ioops slip process prediction scheme corresponding to designated value comprises: according to the frequency monitoring pressure release case liquid level rise situation of normal monitoring nuclear power station, or monitoring pressure release case liquid level rise situation follow the tracks of the trend that pressure release case liquid level goes up;
The described second primary Ioops slip process prediction scheme of leaking designated value corresponding comprises: determine that pressure release case liquid level goes up and occur extremely, checking and determining pressure release case liquid level rise reason.
7. the investigation disposal route that one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed is too fast, is characterized in that, comprising:
Establishment step, according to the corresponding relation of pressure release case liquid level rise speed and primary Ioops slip, be the numerical value identical with the unit of primary Ioops slip by current pressure release case liquid level rise rate transition, and set up the matching relationship of pressure release case liquid level rise speed and primary Ioops slip process prediction scheme;
Select step, according to numerical value, in described matching relationship, select corresponding primary Ioops slip process prediction scheme;
Investigation step, performs the primary Ioops slip process prediction scheme selected, and when determining that the rise of pressure release case liquid level occurs abnormal, checking and determining pressure release case liquid level rise reason.
8. the investigation disposal route that one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed as claimed in claim 7 is too fast, it is characterized in that, in described investigation step, described inspection also determines that pressure release case liquid level rise reason comprises:
Perform safety valve jumping up pressure fixed value checking and tightness test, if School Affairs test findings is defective, then determine that pressure release case liquid level rise reason is the spring safety valve appearance interior leakage phenomenon of chemical volume control system.
9. the investigation disposal route that one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed as claimed in claim 7 is too fast, it is characterized in that, in described investigation step, described inspection also determines that pressure release case liquid level rise reason comprises:
Check the pilot operated safety valve bleeder line temperature of chemical volume control system, judge whether the trend of its temperature occurs rise phenomenon, if there is rise, then determine that pressure release case liquid level rise reason is the pilot operated safety valve appearance interior leakage phenomenon of chemical volume control system.
10. the investigation disposal route that one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed as claimed in claim 7 is too fast, it is characterized in that, in described investigation step, described inspection also determines that pressure release case liquid level rise reason comprises:
Check the pilot operated safety valve bleeder line temperature of reactor RHR system, judge whether the trend of its temperature occurs rise phenomenon, if there is rise, then determine that pressure release case liquid level rise reason is the pilot operated safety valve appearance interior leakage phenomenon of reactor RHR system.
The investigation disposal route that 11. one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed as claimed in claim 7 are too fast, is characterized in that, in described investigation step, described inspection also determines that pressure release case liquid level rise reason comprises:
Check the pilot operated safety valve bleeder line temperature of reactor coolant loop, judge whether the trend of its temperature occurs rise phenomenon, if there is rise, then determine that pressure release case liquid level rise reason is the pilot operated safety valve appearance interior leakage phenomenon of reactor coolant loop.
The investigation disposal route that 12. one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed as claimed in claim 7 are too fast, is characterized in that, in described investigation step, described inspection also determines that pressure release case liquid level rise reason comprises:
Loose joint inspection is performed to the packing of the shower valve of reactor coolant loop, reveals if there is packing, then determine that pressure release case liquid level rise reason is the packing leakage of the shower valve of reactor coolant loop;
Loose joint inspection is performed to the packing of the isolation valve of reactor coolant loop, reveals if there is packing, then determine that pressure release case liquid level rise reason is the packing leakage of the isolation valve of reactor coolant loop.
The investigation disposal route that 13. one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed as claimed in claim 7 are too fast, is characterized in that, in described investigation step, described inspection also determines that pressure release case liquid level rise reason comprises:
Judge whether reactor boron and water make-up system pressure release case liquid level during opening and closing goes up, go up if there is liquid level, then determine that pressure release case liquid level rise reason is the spray isolation valve appearance interior leakage phenomenon of pressure release case.
The investigation disposal route that 14. one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed as claimed in claim 7 are too fast, is characterized in that, in described investigation step, described inspection also determines that pressure release case liquid level rise reason comprises:
Perform the interim operating instruction of xegregating unit cooling water system cooling coil, rise speed before contrasting pressure release case liquid level rise speed and implement during implementing interim operating instruction, if change appears in liquid level rise speed before and after implementing, then determine that pressure release case liquid level rise reason is that component cooling water system cooling coil leaks.
The investigation disposal route that 15. one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed as described in any one of claim 7-14 are too fast, it is characterized in that, the determination of the corresponding relation of described pressure release case liquid level rise speed and primary Ioops slip comprises:
Calculate the per unit slip that per unit liquid level is corresponding, according to result of calculation and historical defect data, determine the corresponding relation of pressure release case liquid level rise speed and primary Ioops slip, described corresponding relation comprises: if pressure release case liquid level rise speed is for being less than first rate designated value, then the primary Ioops slip of its correspondence is for being less than the first leakage designated value, if pressure release case liquid level rise speed is for being more than or equal to first rate designated value and being less than the second speed designated value, then the primary Ioops slip of its correspondence is for being more than or equal to the first leakage designated value, if pressure release case liquid level rise speed is for being more than or equal to the second speed designated value, then the primary Ioops slip of its correspondence is for being more than or equal to the second leakage designated value, wherein said first rate designated value and the second speed designated value set according to historical defect data, described first leakage designated value is the numerical value calculated according to described scaling step and in conjunction with described first rate designated value, described second leakage designated value is the numerical value calculated according to described scaling step and in conjunction with described second speed designated value,
According to the reading of the liquid level gauge be connected with described pressure release case, calculate the slip corresponding with current pressure release case liquid level rise speed, described slip is the numerical value identical with the unit of primary Ioops slip.
The investigation disposal route that 16. one loop of nuclear power station voltage stabilizer pressure release case liquid level rise speed as claimed in claim 15 are too fast, is characterized in that,
Described first leaks primary Ioops slip process prediction scheme corresponding to designated value comprises: according to the frequency monitoring pressure release case liquid level rise situation of normal monitoring nuclear power station, or monitoring pressure release case liquid level rise situation follow the tracks of the trend that pressure release case liquid level goes up;
The described second primary Ioops slip process prediction scheme of leaking designated value corresponding comprises: determine that pressure release case liquid level goes up and occur extremely, checking and determining pressure release case liquid level rise reason.
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