CN106448761B - A kind of nuclear power station safety shell pit filter screen combination property experimental device for verifying - Google Patents
A kind of nuclear power station safety shell pit filter screen combination property experimental device for verifying Download PDFInfo
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- CN106448761B CN106448761B CN201611019797.5A CN201611019797A CN106448761B CN 106448761 B CN106448761 B CN 106448761B CN 201611019797 A CN201611019797 A CN 201611019797A CN 106448761 B CN106448761 B CN 106448761B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
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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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
A kind of nuclear power station safety shell pit filter screen combination property experimental device for verifying, including：Containment sump simulates water tank, with sender property outlet, working medium reflux inlet, charge door；Filter screen module, in containment sump simulation water tank, the working fluid for going out sender property outlet for convection current is filtered；Feed water tank, connects charge door；Branch road, including fuel assembly analogue body are tested, the first fluid mouth of fuel assembly analogue body is connected to sender property outlet, second fluid mouthful and is connected to working medium reflux inlet；Circulating pump, is arranged on sender property outlet to the pipeline between fuel assembly analogue body or fuel assembly analogue body is on the pipeline between working medium reflux inlet.The present invention can cool down the running environment under recycling operating mode for a long time in different disintegrating slag amounts, chemical environment and temperature conditionss Imitating melt pit, the behaviors such as hydraulic characteristic(s), the disintegrating slag blocking characteristic of containment sump filter screen and reactor fuel component are obtained, versatility is good, comprehensive strong, control operation is easy.
Description
Technical field
The present invention relates to the experimental rig field of nuclear device, in particular it relates to which a kind of nuclear power station safety shell pit filter screen is comprehensive
Close performance verification experimental provision.
Background technology
The loss of-coolant accident (LOCA) that last century the nineties foreign countries nuclear power station occurs has triggered Nuclear Safety authorities to filter existing melt pit
The query of net design rationality and the attention to long-term recirculation stage correlative study under reactor large-break LOCA, and open
Series of studies is opened up.
The run case of nuclear power station and subsequent result of study show, are originally directed in melt pit filter screen method of evaluating performance,
There is the understanding of the following aspects not enough：
1）Filter net jam can not be resulted in by filter screen by originally thinking the disintegrating slag of small size, but actually because some are fine
The presence of dimension property material, can form a thinner fibre bed, the fibre bed is by these small sizes in melt pit screen surface
Disintegrating slag produces very strong filtration, and causes its accumulation on filter screen, and melt pit filter screen performance is produced serious influence；
2）Tiny disintegrating slag through melt pit filter screen with emergency reactor cooling system enters reactor core, may enter in fuel assembly
Deposited at mouth or grid spacer, cause core coolant flow is dynamic to be obstructed, the export safely of influence residual heat of nuclear core has to nuclear plant safety
Have a strong impact on；
3）The disintegrating slag quantity that high energy pipeline break the is produced meeting more estimated than originally is more, and disintegrating slag can be more tiny（So it is more easy to
In migration）, and compared with the single kind disintegrating slag of identical quantity, variety classes disintegrating slag（Such as fibrous material and granular substance
Matter）Combination can cause bigger loss in head, and then influence peace note, the available NPSH of peace spray pump；
4）Chemical reaction may also produce disintegrating slag, and this disintegrating slag all very littles, be also possible to produce fibrous material sometimes,
Precipitation produced by chemical reaction can form secondary deposition in the fibre bed of melt pit filter screen or fuel assembly, cause melt pit filter screen
Or the drag characteristic of fuel assembly further deteriorates.
Existing experimental provision single, the low shortcoming of parameter that there is function in the world for melt pit filter screen performance verification, no
It can effectively simulate and be adopted in long-term cooling recycling stage system flow and the change of the working fluid chemical environment, therefore checking analysis
Assumed with more conservative and analyzed, it is impossible to the behavior of disintegrating slag in actual response melt pit recycling phase experiments working medium, led
Cause experimental result overly conservative, the design of melt pit filter screen and transformation to nuclear power station bring larger challenge.
The content of the invention
The purpose of the present invention, which is that, to be overcome the shortcoming and defect of above-mentioned prior art there is provided a kind of comprehensive strong nuclear power
Stand containment sump filter screen combination property experimental device for verifying, can be under the conditions of the chemical environment and temperature change of the working fluid
Simulating pit cools down the running environment under recycling operating mode for a long time, obtains the hydraulic characteristic(s) of containment sump filter screen, disintegrating slag and blocks
The behaviors such as characteristic.
The present invention the used technical scheme that solves the above problems is：
A kind of nuclear power station safety shell pit filter screen combination property experimental device for verifying, including：Containment sump simulates water tank,
With sender property outlet, working medium reflux inlet, charge door；Filter screen module, in containment sump simulation water tank, for convection current
The working fluid for going out sender property outlet is filtered；Fed water tank, and the charging that containment sump simulates water tank is connected to by pipeline
Mouthful；Branch road is tested, the experiment branch road includes fuel assembly analogue body, and one end of fuel assembly analogue body is provided with to be led to for working medium
The first fluid mouthful crossed, the other end is provided with the second fluid mouthful passed through for working medium, first-class inside fuel assembly analogue body
Body mouthful is connected with second fluid mouthful, and the first fluid mouthful of fuel assembly analogue body is connected to sender property outlet, second by pipeline
Body mouthful is connected to working medium reflux inlet by pipeline；Circulating pump, is arranged on the sender property outlet between fuel assembly analogue body
Pipeline on or fuel assembly analogue body on the pipeline between working medium reflux inlet.Containment sump simulation water tank, circulation
Pump, experiment branch road and the pipeline between them constitute the major loop of containment sump filter screen comprehensive performance experimental system.Described
Pipeline between them includes 3 pipelines, is respectively：Containment sump simulates pipeline, the circulating pump between water tank and circulating pump
The pipeline between pipeline, experiment branch road and containment sump simulation water tank between experiment branch road.Containment sump simulation water
Pipeline and circulating pump between case and circulating pump are used for the water intaking pipeline for simulating nuclear power station safety shell pit.Testing branch road is used for mould
Intend nuclear power station safety injection system.
In the technical program, nuclear power station safety shell pit filter screen combination property experimental device for verifying can pass through regulation and control
The chemical environment and addition experiment disintegrating slag of the working fluid, realize this experimental provision in difference in containment sump simulation water tank processed
Run under parameter；Melt pit filter screen performance synthesis under different disintegrating slag amount combinations and chemical environmental conditions can be carried out to test, and fuel
Component blocks hydraulic characteristic(s) experiment；In the case of different chemical environments, disintegrating slag amount recycling can be cooled down for a long time by Simulating pit
Running environment under operating mode, so as to obtain hydraulic characteristic(s), the disintegrating slag blocking characteristic of containment sump filter screen and reactor fuel component
It is comprehensive strong Deng behavior.
As a further improvement on the present invention, electrical heating elements are additionally provided with and cold in the containment sump simulation water tank
But device.In the technical program, nuclear power station safety shell pit filter screen combination property experimental device for verifying further can be adjusted and controlled
The temperature environment of the working fluid in containment sump simulation water tank processed；Can truer simulation different chemical environments,
Melt pit under temperature environment, disintegrating slag amount cools down the running environment under recycling operating mode for a long time, comprehensive strong.
As the another improvement of the present invention, above-mentioned nuclear power station safety shell pit filter screen combination property experimental device for verifying is also wrapped
Disintegrating slag collection system is included, the disintegrating slag collection system includes disintegrating slag collector, and the experiment branch road is between working medium reflux inlet
Pipeline on be provided with the 3rd stop valve, the disintegrating slag collector is in parallel with the 3rd stop valve.Disintegrating slag is set up in the technical program
The disintegrating slag for penetrating filter screen module can be collected when needed after collector, make nuclear power station safety shell pit filter screen combination property
Experimental device for verifying can also carry out the through-flow characteristic test research of melt pit filter screen.
Further, the disintegrating slag collection system also includes the 4th stop valve and the 5th stop valve, and the 4th stop valve, disintegrating slag are received
Storage and the 5th stop valve are in parallel with the 3rd stop valve after being sequentially connected, and the control being opened and closed by these three stop valves can be selected
Whether disintegrating slag collector comes into operation.
Further, above-mentioned nuclear power station safety shell pit filter screen combination property experimental device for verifying is also included with experiment branch road simultaneously
The experiment bypass of connection, the purpose of experiment bypass is simulation nuclear power station spray system.The experiment bypass includes the be sequentially connected
Three flow measurement devices and the 3rd regulating valve.
It is preferred that, the circulating pump is connected to simulates the sender property outlet of water tank between experiment branch road with containment sump
On major loop pipeline.
Further, the outlet of the circulating pump is also associated with being provided with the 6th cut-off on pipeline of sampling, the sampling pipeline
Valve, can carry out sampling research to the working fluid in experimental loop in real time.
Further, the first regulating valve and first flow measurement apparatus, the second regulating valve are additionally provided with the experiment branch road
And second flow measurement apparatus；First regulating valve and first flow measurement apparatus are located at the first fluid mouthful of fuel assembly analogue body
Between the outlet of circulating pump, the second regulating valve and second flow measurement apparatus are located at the second fluid mouthful of fuel assembly analogue body
Between the outlet of circulating pump；The circulating pump and experiment branch road between major loop pipeline on be additionally provided with the 4th regulating valve and
4th flow measurement device.
Further, in addition to the first stop valve and the second stop valve, first stop valve is arranged on circulating pump to experiment
On the pipeline of branch road, second stop valve is connected between circulating pump and the second fluid mouthful of fuel assembly analogue body.Pass through
Adjust the switching of the flow direction of the working fluid in the achievable fuel assembly analogue body of the opening and closing of the first stop valve and the second stop valve.By
Difference is flowed in the working medium of the incoming fuel component under different LOCA cuts and injection operating mode, the mesh for flowing to switching construction is set
Be that the flow direction of working medium in fuel assembly analogue body in experimental provision can be realized according to different LOCA cuts and injection operating mode
Switching.
Further, above-mentioned nuclear power station safety shell pit filter screen combination property experimental device for verifying also includes thermal parameter measurement
Control device, the first pressure difference transmitter, the second pressure difference transmitter, second pressure difference transmitter respectively with fuel assembly analogue body
First fluid mouthful and second fluid mouthful be connected, measure the first fluid mouthful of fuel assembly analogue body and the working medium of second fluid mouth
Pressure difference, first pressure difference transmitter is connected with the entrance and exit of filter screen module, measures the entrance and exit of filter screen module
Working medium pressure difference；Thermometer, the thermal parameter measuring and controlling and temperature are additionally provided with the containment sump simulation water tank
Spend meter, the first pressure difference transmitter, the second pressure difference transmitter, first flow measurement apparatus, second flow measurement apparatus to be connected, connect
Receive thermal parameter measurement signal；The thermal parameter measuring and controlling is also connected with the first regulating valve, the second regulating valve, output
Thermal parameter control signal.
To sum up, the beneficial effects of the invention are as follows：
1st, nuclear power station safety shell pit filter screen combination property experimental device for verifying of the invention can pass through regulation and control
The chemical environment of the working fluid, temperature environment and addition experiment disintegrating slag, realize that this experiment is filled in containment sump simulation water tank
Put and run under different parameters；Melt pit filter screen performance under the combination of different disintegrating slag amounts, temperature environment and chemical environmental conditions can be carried out
Comprehensive Experiment, and fuel assembly block hydraulic characteristic(s) experiment；Can be in different disintegrating slag amounts, chemical environment and temperature change condition
Imitating melt pit cools down the running environment under recycling operating mode for a long time, so as to obtain containment sump filter screen and reactor fuel component
The behavior such as hydraulic characteristic(s), disintegrating slag blocking characteristic, it is comprehensive strong；
2nd, the present invention sets up after disintegrating slag collector and the disintegrating slag for penetrating filter screen module can be collected when needed, makes nuclear power
Containment sump filter screen combination property of standing experimental device for verifying can also carry out the through-flow characteristic test research of melt pit filter screen；
3rd, the present invention can be adapted to without heap by changing different type sump filter module and fuel assembly analogue body
The checking of type needs, highly versatile, and control operation is easy, experimental performance is good.
Brief description of the drawings
Fig. 1 is the structural representation of one embodiment of the present of invention；
Fig. 2 is the structural representation of the nuclear power station safety shell pit filter screen combination property experimental device for verifying in embodiment 6.
Mark and corresponding parts title in accompanying drawing：1- containment sumps simulate water tank；2- filter screen modules；3- is circulated
Pump；4- fuel assembly analogue bodies；5- disintegrating slag collectors；101- electrical heating elements；102- coolers；103- agitators；301-
Seven stop valves；The regulating valves of 302- the 4th；The flow measurement devices of 304- the 4th；The stop valves of 305- first；The stop valves of 407- second；
The regulating valves of 401- first；402- first flow measurement apparatus；The regulating valves of 403- the 3rd；The flow measurement devices of 404- the 3rd；405-
Second regulating valve；406- second flow measurement apparatus；The stop valves of 501- the 3rd；The stop valves of 502- the 4th；The stop valves of 503- the 5th；
504- three-way pipes A；505- three-way pipes B；The flexible pipes of 601- first；The flexible pipes of 701- second；The charging water tanks of 6- first；The charging water of 7- second
Case；The stop valves of 8- the 6th；9- air bleeding valves；10- thermal parameter measuring and controllings；11- thermometers；The pressure difference transmitters of 12- first；
The pressure difference transmitters of 13- second.
Embodiment
The present invention will now be described in further detail with reference to the accompanying drawings and the accompanying drawings, but embodiments of the present invention
Not limited to this.
Embodiment 1：
As shown in figure 1, a kind of nuclear power station safety shell pit filter screen combination property experimental device for verifying, including containment sump
Simulate water tank 1, filter screen module 2, charging water tank, circulating pump 3 and experiment branch road.
Containment sump simulation water tank 1 is used for the melt pit of simulating Safety shell, its internal reservoir the working fluid and with working medium
Outlet, working medium reflux inlet, two charge doors.
Charging water tank is connected to the charge door that containment sump simulates water tank 1 by pipeline, by the experiment disintegrating slag configured
And chemical reagent injection containment sump simulation water tank 1；2 charging water tanks are set in the present embodiment, are the first charging water respectively
The charging water tank 7 of case 6, second, a charging water tank simulates the injection testing disintegrating slag of water tank 1 to containment sump, another charging water
Case is connected to charge door to the containment sump simulation injection chemical reagent of water tank 1, the first charging water tank 6 by the first flexible pipe 601,
Second charging water tank 7 is connected to charge door by the first flexible pipe 701, and two charging water tanks coordinate to be needed to configure according to experiment
Experiment disintegrating slag and chemical reagent pass through flexible flexible pipe and inject containment sump and simulate water tank 1.
Filter screen module 2 is arranged in containment sump simulation water tank 1, and sender property outlet is gone out using filter screen convection current to be tested
The working fluid is filtered, and the setting of filter screen can use the common mounting means of melt pit, i.e. filter screen module 2 to set a filtering
Pond, filter screen is arranged on the working fluid after all filterings in filtering ponds entrance, filtering ponds.
Sender property outlet, circulating pump 3, experiment branch road, the containment sump of containment sump simulation water tank 1 simulate water tank 1
Working medium reflux inlet is sequentially connected；I.e. circulating pump 3 is arranged on the sender property outlet to the major loop pipeline between experiment branch road,
For extracting the working fluid supply experiment branch road after filtering in the filter tank for the filter screen module 2 that water tank 1 is simulated from containment sump.
Circulating pump 3 connects containment sump by pipeline and simulates water tank 1, and connected mode has 2 kinds：One kind is pipeline directly by containment
The sender property outlet of melt pit simulation water tank 1 is connected in filtering ponds, and another is to set pipeline or runner to be connected in filtering ponds
Sender property outlet, circulating pump 3 connects sender property outlet by pipeline；Circulating pump 3 and circulating pump 3 and containment sump simulation water tank 1 it
Between pipeline be used to simulate the water intaking pipeline of nuclear power station safety shell pit.
Experiment branch road is used to simulate nuclear power station safety injection system, and it includes the first regulating valve 401, the first flow being sequentially connected
Measurement apparatus 402, fuel assembly analogue body 4, the second regulating valve 405, second flow measurement apparatus 406.Fuel assembly analogue body 4
One end be provided with the first fluid mouthful passed through for the working fluid, the other end is provided with the second fluid passed through for the working fluid
Mouthful, inside fuel assembly analogue body 4, first fluid mouthful is connected with second fluid mouthful, passes through the working fluid first-class
Body mouthful flows into fuel assembly analogue body 4, fuel assembly analogue body 4 is flowed out by second fluid mouthful or leads to the working fluid
Cross second fluid mouthful and flow into fuel assembly analogue body 4, by first fluid mouthful outflow fuel assembly analogue body 4.Fuel assembly mould
The first fluid mouthful of plan body 4 is connected to circulating pump 3, second fluid mouth by pipeline and is connected to the working medium by pipeline and passes back into
Mouthful；First regulating valve 401, first flow measurement apparatus 402 are arranged on first fluid mouthful between circulating pump 3 on pipeline, and first
The entrance of regulating valve 401 connects circulating pump 3 by pipeline, and first flow measurement apparatus 402 is connected to the first regulating valve 401 and combustion
Between the first fluid mouthful for expecting component analogue body 4；Second regulating valve 405, second flow measurement apparatus 406 are located at second fluid mouthful
Onto the pipeline between working medium reflux inlet, second flow measurement apparatus 406 connects containment sump by pipeline and simulates water tank 1
Working medium reflux inlet, the second fluid mouthful that the second regulating valve 405 is connected to fuel assembly analogue body 4 measures with second flow and fills
Put between 406.
Agitator 103 is also set up in containment sump simulation water tank 1, it is ensured that the experiment disintegrating slag and chemical reagent of injection are in peace
Uniformly mixed with the working fluid in full shell melt pit simulation water tank 1.
Electrical heating elements 101 and cooler 102 are additionally provided with containment sump simulation water tank 1, for realizing to experiment
The temperature control of working medium.
Between containment sump simulation water tank 1, circulating pump 3, experiment branch road, containment sump simulation water tank 1 and circulating pump 3
Pipeline, circulating pump 3 and experiment branch road between pipeline, experiment branch road and containment sump simulation water tank 1 between pipeline structure
Into the major loop of containment sump filter screen comprehensive performance experimental system.
The operation principle of above-mentioned nuclear power station safety shell pit filter screen combination property experimental device for verifying is：
During experiment, containment sump simulation water tank 1 stores a certain amount of the working fluid, according to experiment demand, passes through charging
The working fluid that water tank is simulated to containment sump in water tank 1 adds chemical reagent and/or disintegrating slag, is stirred by agitator 103
Uniformly, filter screen module 2 uses the filter screen tested to that will flow out the experiment work that containment sump simulates water tank 1 from sender property outlet
Matter is filtered, and circulating pump 3 simulates water tank 1 from containment sump and takes out the working fluid supply experiment branch after being filtered through filter screen 2
Road, the working fluid, which is flowed through, turns again to containment sump simulation water tank 1 after experiment branch road, form closed-loop path.
Nuclear power station safety shell pit filter screen combination property experimental device for verifying in the present embodiment can pass through regulation and control
The chemical environment and addition experiment disintegrating slag of the working fluid, pass through the He of electrical heating elements 101 in containment sump simulation water tank 1 processed
Cooler 102 configures the temperature environment of the working fluid, realizes that this experimental provision is run under different parameters；Different disintegrating slags can be carried out
Melt pit filter screen performance synthesis is tested under amount combination and chemical environmental conditions, and fuel assembly blocks hydraulic characteristic(s) experiment；Can
Simulating pit cools down the operation ring under recycling operating mode for a long time under the conditions of the working fluid volume, chemical environment and temperature change
Border, so that the behaviors such as hydraulic characteristic(s), the disintegrating slag blocking characteristic of containment sump filter screen and reactor fuel component are obtained, it is comprehensive
By force.
In above-mentioned application, according to the actual requirements, circulating pump 3 can also be arranged on experiment branch road to working medium reflux inlet it
Between pipeline on.
Embodiment 2：
On the basis of embodiment 1, a kind of nuclear power station safety shell pit filter screen combination property checking in the present embodiment is real
Experiment device also includes being provided with the 3rd cut-off on disintegrating slag collection system, the experiment branch road to the pipeline between working medium reflux inlet
Valve 501；The disintegrating slag collection system is in parallel with the 3rd stop valve 501.
The disintegrating slag collection system includes 2 disintegrating slag collectors 5, the 4th stop valve 502, the 5th stop valve 503, three-way pipes
B505, three-way pipe A504；Three-way pipe A504 has an entrance and two outlets, and three-way pipe A504 entrance connection the 4th ends
The outlet of valve 502, the entrance of three-way pipe A two each connections in outlet, one disintegrating slag collector 5；Three-way pipe B505 has two and entered
Mouth and 1 outlet, two entrance respectively connect the outlet of a disintegrating slag collector 5, and its outlet connects entering for the 5th stop valve 503
Mouthful；The entrance of 4th stop valve 502 is connected on the pipeline between the 3rd stop valve 501 and experiment branch road；5th stop valve 503
It is connected on the pipeline that the 3rd stop valve 501 is simulated to containment sump between water tank 1.So that 2 disintegrating slag collectors 5
Entrance is connected by three-way pipe A504 and the pipeline of upstream, insert experiment working medium；The outlet of 2 disintegrating slag collectors 5 passes through threeway
Pipe B505 and the pipeline in downstream are connected, and export the working fluid.
The online switching of two disintegrating slag collectors 5 can be realized by three-way pipe B505, three-way pipe A504；Pass through the 3rd cut-off
Enabling and bypassing for disintegrating slag collection system can be achieved in valve 501, the 4th stop valve 502, the opening and closing of the 5th stop valve 503.
Disintegrating slag collector 5 in the present embodiment is mainly used in collecting the disintegrating slag for flowing through disintegrating slag collection system, and its structure can be with
Using disintegrating slag filter commonly used in the prior art, repeated no more in the present embodiment.
Disintegrating slag collector 5 is collected to the disintegrating slag for penetrating filter screen module 2 when needed, therefore the nuclear power station in the present embodiment
Containment sump filter screen combination property experimental device for verifying can also carry out melt pit filter screen by the application of disintegrating slag collection system and lead to
Properties of flow experimental study.
Each individual event of system collection of nuclear power station safety shell pit filter screen combination property experimental device for verifying in the present embodiment is real
Check system is comprehensive strong in one.
Embodiment 3：
On the basis of embodiment 1 or embodiment 2, a kind of nuclear power station safety shell pit filter screen in the present embodiment is comprehensive
The experiment that being able to verify that experimental provision is also included with testing branch circuit parallel connection is bypassed, and the experiment bypass is used to simulate nuclear power station safety spray system
System, it includes the 3rd flow measurement device 404 being sequentially connected and the 3rd regulating valve 403.
The 4th regulating valve 302 and the are also disposed with major loop pipeline between the circulating pump 3 and experiment branch road
Four flow measurement devices 304, the 4th regulating valve 302 is connected with circulating pump 3, and the downstream of the 4th flow measurement device 304 is connected simultaneously
3rd flow measurement device 404 and the first regulating valve 401；3rd regulating valve 403 is connected under the 3rd flow measurement device 404
Trip.
In the present embodiment, the working fluid come out from circulating pump 3 is measured by the 4th flow measurement device 304 is divided to two after flow
Road, is all the way experiment bypass, and the working fluid can be directly by testing bypass outflow；Another road is experiment branch road, flows into experiment
The working fluid of branch road is measured after flow by the first regulating valve 401, by first flow measurement apparatus 402, passes sequentially through reactor core
Fuel assembly analogue body 4, the second regulating valve 405, second flow measurement apparatus 406 flow out；Test branch road and experiment bypass outflow
The working fluid converge to again flow back to together containment sump simulation water tank 1, formed closed-loop path.
Embodiment 4：
On the basis of any of the above-described embodiment, a kind of nuclear power station safety shell pit filter screen combination property in the present embodiment
Experimental device for verifying also includes the first stop valve 305 and the second stop valve 407, and first stop valve 305 is arranged on circulating pump 3
Onto the pipeline of experiment branch road, second stop valve 407 is connected to the second fluid of circulating pump 3 and fuel assembly analogue body 4
Between mouthful.Opening and closing by adjusting the first stop valve 305 and the second stop valve 407 can be achieved to test in fuel assembly analogue body 4
The switching of the flow direction of working medium.Because the working medium of the incoming fuel component under different LOCA cuts and injection operating mode flows to difference,
Setting flows to switching construction and can realized according to different LOCA cuts and injection operating mode in experimental provision in fuel assembly analogue body 4
The switching of the flow direction of working medium.
Embodiment 5：
As shown in figure 1, a kind of nuclear power station safety shell pit filter screen combination property experimental device for verifying, including containment sump
Simulate water tank 1, filter screen module 2, charging water tank, circulating pump 3, experiment branch road, experiment bypass.
Containment sump simulation water tank 1 is used for the melt pit of simulating Safety shell, its internal reservoir the working fluid and with working medium
Outlet, working medium reflux inlet, charge door.
The setting of charging water tank and charge door can be using any of following 2 kinds of modes：（1）Containment sump is simulated
2 charge doors are set on water tank, and charging water tank quantity is 2：The first charging charging water tank 7 of water tank 6, second, a charging water
Case simulates the injection testing disintegrating slag of water tank 1 to containment sump, and another charging water tank simulates the injectionization of water tank 1 to containment sump
Learn reagent；（2）1 charge door is set on containment sump simulation water tank, and charging water tank quantity is 1, and charging water tank passes through pipe
Line is connected to the charge door that containment sump simulates water tank 1, by the experiment disintegrating slag and chemical reagent that have configured with injecting containment
Hole simulation water tank 1.Filter screen module 2 is arranged in containment sump simulation water tank 1, and the experiment of sender property outlet is gone out using filter screen convection current
Working medium is filtered.
Agitator 103, electrical heating elements 101 and cooler 102 are also set up in containment sump simulation water tank 1.
Sender property outlet, circulating pump 3, experiment branch road, the containment sump of containment sump simulation water tank 1 simulate water tank 1
Working medium reflux inlet is sequentially connected；The 7th stop valve is provided with pipeline between circulating pump 3 and containment sump simulation water tank 1
301；Empirically the flow direction of working medium is disposed with the 4th regulating valve the 302, the 4th on pipeline between circulating pump 3 and experiment branch road
Flow measurement device 304, the first stop valve 305；The is provided with experiment branch road to the pipeline between working medium reflux inlet
Three stop valves 501.
Experiment branch road includes the first regulating valve 401, first flow measurement apparatus 402, the fuel assembly simulation being sequentially connected
Body 4, the second regulating valve 405, second flow measurement apparatus 406, the entrance of the first regulating valve 401 are ended by pipeline connection first
Valve 305, second flow measurement apparatus 406 connects the 3rd stop valve 501 by pipeline.
The disintegrating slag collection system is in parallel with the 3rd stop valve 501, and disintegrating slag collection system includes 2 disintegrating slag collectors 5, the
Four stop valves 502, the 5th stop valve 503, three-way pipe B505, three-way pipe A504；Three-way pipe A504 has an entrance and two
Outlet, three-way pipe A504 entrance connects the outlet of the 4th stop valve 502, three-way pipe A two each connections in outlet, one disintegrating slag
The entrance of collector 5；Three-way pipe B505 has two entrances and 1 outlet, and two entrance respectively connects a disintegrating slag collector 5
Outlet, its export connection the 5th stop valve 503 entrance；The entrance of 4th stop valve 502 be connected to the 3rd stop valve 501 with
On pipeline between second flow measurement apparatus 406；5th stop valve 503 is connected to the 3rd stop valve 501 to containment sump
Simulate on the pipeline between the working medium reflux inlet of water tank 1.
Experiment bypass and experiment branch circuit parallel connection, including the 3rd flow measurement device 404 and the 3rd regulating valve 403, the 3rd stream
Measuring device 404 is connected between the first stop valve 305 and the 3rd regulating valve 403, and the outlet of the 3rd regulating valve 403 passes through pipeline
Connect the entrance of the 3rd stop valve 501 and the 4th stop valve 502.
One end of fuel assembly analogue body 4 is provided with the first fluid mouthful passed through for the working fluid, and the other end is provided with confession
The second fluid mouthful that the working fluid passes through, inside fuel assembly analogue body 4, first fluid mouthful is connected with second fluid mouthful, is made
The working fluid can be flowed into fuel assembly analogue body 4 by first fluid mouthful, be simulated by second fluid mouthful outflow fuel assembly
Body 4 or, the working fluid is flowed into fuel assembly analogue body 4 by second fluid mouthful, fired by first fluid mouthful outflow
Expect component analogue body 4.The first fluid mouthful of fuel assembly analogue body 4 connects first flow measurement apparatus 402, second by pipeline
Fluid flow port connects the second regulating valve 405 by pipeline.
4th flow measurement device 304 is additionally provided with second section between the second fluid mouthful of fuel assembly analogue body 4
Only valve 407, the entrance of the second stop valve 407 is connected the 4th flow measurement by pipeline with the entrance of the first stop valve 305 and filled
Put 304.
The second fluid mouth of the fuel assembly analogue body 4 is also associated with air bleeding valve 9, and air bleeding valve 9 is carried out to experimental loop
Exhaust, it is ensured that the security of whole experimental loop；The outlet of the circulating pump 3 is also associated with sample pipeline, the sampling pipeline
On be provided with the 6th stop valve 8, by the 6th stop valve 8 can experiment carry out during to the working fluid carry out real time sample.
Embodiment 6：
On the basis of embodiment 5, as shown in Fig. 2 a kind of nuclear power station safety shell pit filter screen in the present embodiment is integrated
Performance verification experimental provision also includes thermal parameter measuring and controlling 10, the first pressure difference transmitter 12, the second pressure difference transmitter
13.Second pressure difference transmitter 13 is connected with the first fluid mouthful and second fluid mouthful of fuel assembly analogue body 4 respectively, measures
The working medium pressure difference of first fluid mouthful and the second fluid mouth of fuel assembly analogue body 4, first pressure difference transmitter 12 and filter screen
2 entrance and exits of module are connected, and measure the working medium pressure difference of 2 entrance and exits of filter screen module.
Thermometer 11 is additionally provided with the containment sump simulation water tank 1.The thermal parameter measuring and controlling 10
Measured with thermometer 11, the first pressure difference transmitter 12, the second pressure difference transmitter 13, first flow measurement apparatus 402, second flow
Device 406, the 3rd flow measurement device 404, the 4th flow measurement device 304 are connected, and receive temperature, gas that they are gathered
The thermal parameter measurement signal such as pressure, flow；The thermal parameter measuring and controlling 10 is also adjusted with the first regulating valve 401, second
Save valve 405, the 3rd regulating valve 403, the 4th regulating valve 302 to be connected, the thermal parameter control signal such as output temperature, flow, temperature
Control signal is sent to the control device of electrical heating elements 101 and cooler 102, and flow control signal is sent to corresponding first
Regulating valve 401, the second regulating valve 405, the 3rd regulating valve 403, the 4th regulating valve 302.
Thermal parameter measuring and controlling 10 counts the working medium temperature adopted in control system completion containment sump simulation water tank 1
The function of degree, the control of loop flow and regulation.
The first regulating valve 401, the second regulating valve 405, the 3rd regulating valve 403, the 4th regulating valve 302 in the present embodiment are adopted
Use electric control valve；First stop valve 305, the second stop valve 407, the 3rd stop valve 501, the cut-off of the 4th stop valve the 502, the 5th
Valve 503, the 6th stop valve 8, the 7th stop valve 301 use hand stop valve, and first flow measurement apparatus 402, second are measured
Measure device 406, the 3rd flow measurement device 404, the 4th flow measurement device 304 and use flowmeter.
In the present embodiment, filter screen module 2 is installed in containment sump simulation water tank 1, water tank configures containment by feeding
The chemical environment and addition experiment disintegrating slag of the working fluid, pass through electrical heating elements 101 and cooler in melt pit simulation water tank 1
The temperature environment of 102 configuration the working fluids；The working fluid containing disintegrating slag is stirred in containment sump simulation water tank 1
Enter the entrance of circulating pump 3 after being filtered afterwards by filter screen module 2, circulating pump 3 is exported through the 4th regulating valve 302, the 4th flow measurement
It is divided into two branch roads after the stop valve 305 of device 304 and first, a branch road is experiment branch road, and another branch road bypasses for experiment,
The working fluid of two branch road outflows returns to containment sump simulation water tank 1 after converging through disintegrating slag collection system, and formation is closed back
Road.
Present embodiments providing one kind can be cold for a long time in different disintegrating slag amounts, chemical environment and temperature conditionss Imitating melt pit
But the running environment under operating mode is recycled, so as to obtain hydraulic characteristic(s), the disintegrating slag of containment sump filter screen and reactor fuel component
The containment sump filter screen combination property experimental device for verifying of the behaviors such as blocking characteristic, by simulating LOCA（Dehydration）After accident
Hole recycling phase security shell the working fluid in disintegrating slag under the working fluid chemical environmental conditions in containment sump filter screen and combustion
Blocking, depositing behavior on material component, understand the physical clogging performance and chemical precipitation pick-up behavior of disintegrating slag, grasp disintegrating slag and block
Under the conditions of containment sump filter screen and reactor core hydraulic characteristic(s).The design that achievement in research is used for nuclear power station safety shell pit filter screen is tested
Card, it is ensured that containment sump filter screen performance meets the safety discharge of melt pit recycling stage residual heat of nuclear core after LOCA accident.The dress
Replaceable different type sump filter module and fuel assembly analogue body are put to adapt to the checking needs without heap-type, and is controlled
Make easy to operate, experimental performance good.
It the above is only the preferred embodiment of the present invention, protection scope of the present invention is not limited merely to above-described embodiment,
All technical schemes belonged under thinking of the present invention belong to protection scope of the present invention.It should be pointed out that for the art
For those of ordinary skill, some improvements and modifications without departing from the principles of the present invention should be regarded as the protection of the present invention
Scope.
Claims (10)
1. a kind of nuclear power station safety shell pit filter screen combination property experimental device for verifying, it is characterised in that including：
Containment sump simulates water tank（1）, with sender property outlet, working medium reflux inlet, charge door；
Filter screen module（2）, water tank is simulated installed in containment sump（1）Interior, the working fluid for going out sender property outlet for convection current is entered
Row filtering；
Feed water tank, and being connected to containment sump by pipeline simulates water tank（1）Charge door；
Branch road is tested, the experiment branch road includes fuel assembly analogue body（4）, fuel assembly analogue body（4）One end be provided with
The first fluid mouthful passed through for working medium, the other end is provided with the second fluid mouthful passed through for working medium, in fuel assembly analogue body（4）
Inside, first fluid mouthful is connected with second fluid mouthful, fuel assembly analogue body（4）First fluid mouthful institute is connected to by pipeline
State sender property outlet, second fluid mouthful and the working medium reflux inlet is connected to by pipeline；
Circulating pump（3）, the sender property outlet is arranged on to fuel assembly analogue body（4）Between pipeline on or fuel assembly mould
Intend body（4）Onto the pipeline between working medium reflux inlet；
Containment sump simulates water tank（1）, circulating pump（3）, experiment branch road and pipeline between them constitute containment sump filter
The major loop of net comprehensive performance experimental system.
2. a kind of nuclear power station safety shell pit filter screen combination property experimental device for verifying according to claim 1, its feature
It is, the containment sump simulates water tank（1）Inside it is additionally provided with electrical heating elements（101）And cooler（102）.
3. a kind of nuclear power station safety shell pit filter screen combination property experimental device for verifying according to claim 1, its feature
It is, in addition to disintegrating slag collection system, the disintegrating slag collection system includes disintegrating slag collector（5）, the experiment branch road to working medium
The 3rd stop valve is provided with pipeline between reflux inlet（501）, the disintegrating slag collector（5）With the 3rd stop valve（501）
It is in parallel.
4. a kind of nuclear power station safety shell pit filter screen combination property experimental device for verifying according to claim 3, its feature
It is, the disintegrating slag collection system also includes the 4th stop valve（502）With the 5th stop valve（503）, the 4th stop valve（502）、
Disintegrating slag collector（5）With the 5th stop valve（503）With the 3rd stop valve after being sequentially connected（501）It is in parallel.
5. according to a kind of any described nuclear power station safety shell pit filter screen combination property experimental device for verifying of Claims 1-4,
Characterized in that, the experiment also included with testing branch circuit parallel connection is bypassed, the experiment bypass includes the 3rd flow being sequentially connected
Measurement apparatus（404）With the 3rd regulating valve（403）.
6. according to a kind of any described nuclear power station safety shell pit filter screen combination property experimental device for verifying of Claims 1-4,
Characterized in that, the circulating pump（3）It is connected to and simulates water tank with containment sump（1）Sender property outlet to experiment branch road between
Major loop pipeline on.
7. a kind of nuclear power station safety shell pit filter screen combination property experimental device for verifying according to claim 6, its feature
It is, the circulating pump（3）Outlet be also associated with pipeline of sampling, be provided with the 6th stop valve on the sampling pipeline（8）.
8. a kind of nuclear power station safety shell pit filter screen combination property experimental device for verifying according to claim 6, its feature
It is, in addition to the first stop valve（305）With the second stop valve（407）, first stop valve（305）It is arranged on circulating pump
（3）Onto the pipeline of experiment branch road, second stop valve（407）It is connected to circulating pump（3）With fuel assembly analogue body（4）'s
Between second fluid mouthful.
9. a kind of nuclear power station safety shell pit filter screen combination property experimental device for verifying according to claim 6, its feature
It is, the first regulating valve is additionally provided with the experiment branch road（401）And first flow measurement apparatus（402）, the second regulating valve
（405）And second flow measurement apparatus（406）；First regulating valve（401）And first flow measurement apparatus（402）Positioned at fuel stack
Part analogue body（4）First fluid mouthful and circulating pump（3）Outlet between, the second regulating valve（405）And second flow measurement dress
Put（406）Positioned at fuel assembly analogue body（4）Second fluid mouthful and circulating pump（3）Outlet between；The circulating pump（3）With
The 4th regulating valve is additionally provided with major loop pipeline between experiment branch road（302）And the 4th flow measurement device（304）.
10. a kind of nuclear power station safety shell pit filter screen combination property experimental device for verifying according to claim 9, its feature
It is, in addition to thermal parameter measuring and controlling（10）, the first pressure difference transmitter（12）, the second pressure difference transmitter（13）, institute
State containment sump simulation water tank（1）Inside it is additionally provided with thermometer（11）, second pressure difference transmitter（13）Respectively with fuel
Component analogue body（4）First fluid mouthful and second fluid mouthful be connected, measurement fuel assembly analogue body（4）First fluid mouthful and
The working medium pressure difference of second fluid mouthful, first pressure difference transmitter（12）With filter screen module（2）Entrance and exit be connected, measurement
Filter screen module（2）Entrance and exit working medium pressure difference；The thermal parameter measuring and controlling（10）With thermometer（11）,
One pressure difference transmitter（12）, the second pressure difference transmitter（13）, first flow measurement apparatus（402）, second flow measurement apparatus
（406）It is connected, receives thermal parameter measurement signal；The thermal parameter measuring and controlling（10）Also with the first regulating valve
（401）, the second regulating valve（405）It is connected, exports thermal technology's parameter control signal.
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| CN107221362B (en) * | 2017-04-27 | 2021-06-18 | 中国核电工程有限公司 | Pit filter performance evaluation experimental system |
| CN107340218B (en) * | 2017-06-05 | 2020-06-30 | 中广核研究院有限公司 | Test system for researching downstream effect in CPR1000 pit filter screen pile |
| CN108361375B (en) * | 2018-02-13 | 2019-07-09 | 中国核动力研究设计院 | Visualization segmented seal cylinder for nuclear power plant's chemical effect research |
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| JPH11337677A (en) * | 1998-05-28 | 1999-12-10 | Hitachi Ltd | Performance calculator for reactor core |
| JP2003161796A (en) * | 2001-11-27 | 2003-06-06 | Global Nuclear Fuel-Japan Co Ltd | Method and device for evaluating thermal characteristics of fuel rod |
| EP2077561A1 (en) * | 2008-01-01 | 2009-07-08 | Institute of Nuclear Energy Research Atomic Energy Council, Executive Yuan | Thermal limit analysis with hot-channel model for boiling water reactors |
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| CN104979025B (en) * | 2015-06-30 | 2017-07-07 | 浙江工业大学 | Structural intergrity test platform under the conditions of a kind of reactor pressure vessel IVR |
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