CN202886079U - Sealing performance test device of mechanical penetration pieces of safety shell in nuclear power station - Google Patents
Sealing performance test device of mechanical penetration pieces of safety shell in nuclear power station Download PDFInfo
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- CN202886079U CN202886079U CN2012205703917U CN201220570391U CN202886079U CN 202886079 U CN202886079 U CN 202886079U CN 2012205703917 U CN2012205703917 U CN 2012205703917U CN 201220570391 U CN201220570391 U CN 201220570391U CN 202886079 U CN202886079 U CN 202886079U
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- 230000035515 penetration Effects 0.000 title claims abstract description 36
- 238000007789 sealing Methods 0.000 title claims abstract description 7
- 238000011056 performance test Methods 0.000 title abstract 3
- 238000012360 testing method Methods 0.000 claims abstract description 127
- 230000001105 regulatory effect Effects 0.000 claims abstract description 20
- 230000008878 coupling Effects 0.000 claims description 20
- 238000010168 coupling process Methods 0.000 claims description 20
- 238000005859 coupling reaction Methods 0.000 claims description 20
- 238000000034 method Methods 0.000 claims description 16
- 208000027418 Wounds and injury Diseases 0.000 claims description 4
- 230000008859 change Effects 0.000 claims description 4
- 230000006378 damage Effects 0.000 claims description 4
- 230000000694 effects Effects 0.000 claims description 4
- 208000014674 injury Diseases 0.000 claims description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 4
- 238000007664 blowing Methods 0.000 claims description 3
- 238000000151 deposition Methods 0.000 claims description 3
- 238000007599 discharging Methods 0.000 claims description 3
- 210000003141 lower extremity Anatomy 0.000 claims description 3
- 239000007789 gas Substances 0.000 description 23
- 238000013461 design Methods 0.000 description 9
- 230000005855 radiation Effects 0.000 description 6
- 230000008569 process Effects 0.000 description 4
- 238000012795 verification Methods 0.000 description 4
- 230000007423 decrease Effects 0.000 description 3
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 2
- 230000006835 compression Effects 0.000 description 2
- 238000007906 compression Methods 0.000 description 2
- 238000012937 correction Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000002955 isolation Methods 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 238000011084 recovery Methods 0.000 description 2
- 238000000429 assembly Methods 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000002596 correlated effect Effects 0.000 description 1
- 238000012938 design process Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 229910052757 nitrogen Inorganic materials 0.000 description 1
- 238000010926 purge Methods 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 238000010998 test method Methods 0.000 description 1
- 230000007306 turnover Effects 0.000 description 1
- 238000011144 upstream manufacturing Methods 0.000 description 1
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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
The utility model discloses a sealing performance test device of mechanical penetration pieces of a safety shell in a nuclear power station. The sealing performance test device comprises a gas storage tank, a float flow meter, a pressure gauge and an electronic stopwatch. One end of a test connection joint L01 is connected with a gas cylinder, and the other end of the L01 is connected to the inlet of a valve V01 of a compressed air regulating valve; the outlet of the valve 01 of a plug valve is connected to the inlets of the valve V02 and the valve V03; the outlet of the valve V02 of the plug valve is connected with a clamp-type quick joint N01, and then connected to the inlet of the gas storage tank; the outlet of the gas storage tank is connected with the clamp-type quick joint N02, and then connected to the inlet of the valve V4 of the plug valve; after the outlets of the valves V3 and V4 of the plug valve are converged to one pipeline, the pipeline is divided into two pipelines, and the two pipelines are respectively connected to the inlets of the valves V05 and V07 of the plug valve; the outlet pipelines of the plug valve are divided into two pipelines. The device adopts the movable pull-rod box form, and rationally distributes each part of the test device. The instruments to be tested and the system devices are quickly connected in a clamping manner so as to conveniently detach and install.
Description
Technical field
The utility model relates to a kind of nuclear power plant containment shell machinery penetration piece leak tightness test device that carries out, and is used for carrying out nuclear power plant containment shell machinery penetration piece isolation valve leak rate test.
Background technology
The containment of nuclear power station has the radioactive shield function, guarantees its sealing to prevent that radiomaterial is discharged in the environment, Protection personnel and public security under the accident conditionses such as a loop large break and secondary circuit vapour line large break.The pipeline of turnover containment should be able to be isolated in above-mentioned accident, to guarantee the integrality of containment.Generally the containment outside be isolating door, the inboard is isolating door or non-return flap.
For guaranteeing the tightness of this valve, the nuclear power station staff needs regularly this valve to be carried out impermeability test, is nuclear power plant containment shell machinery penetration piece impermeability test.But because the type of the nuclear power station of China is various at present, the acceptance criteria of the nuclear power plant containment shell machinery penetration piece impermeability test of each type is not identical.Therefore, relevant nuclear power plant containment shell machinery penetration piece impermeability test all is to take interim test unit.This so that the nuclear power station staff before carrying out nuclear power plant containment shell machinery penetration piece impermeability test, all to reselect and apparatus for assembling.This not only needs the related personnel to the inspections such as impermeability of being correlated with of the test unit of each assembling, simultaneously because different facilities is all taked in each test, also have great impact for the repeatability of test and result's comparability, the accuracy of test findings also often is under suspicion.Simultaneously, present domestic nuclear power carries out nuclear power plant containment shell machinery penetration piece impermeability test and adopts the interim trial apparatus structure loose, not portable, operate also very inconvenient, this has increased greatly test clerk and has carried out time of test operation at reactor building, has increased testing crew in the hold-up time of radiation control zone and has been subject to radiation risk.
Summary of the invention
In order to overcome the problem such as various, loosely organized, the not portable and operation inconvenience of present nuclear power plant containment shell machinery penetration piece leak tightness test device, the utility model provides a kind of nuclear power plant containment shell machinery penetration piece leak tightness test device according at present general nuclear power plant containment shell machinery penetration piece impermeability test principle.This installs not only, and structural member gathers, easy to use, and be applicable at present all nuclear power plant containment shells machinery penetration piece impermeability tests, the repeatability of test also strengthens greatly, the running time of test also can shorten, greatly reduce the test operation personnel in the hold-up time of radiation area, strengthened the radiated time protection, reduced the risk that the staff is subject to radiant quantity.
The technical scheme that its technical matters that solves the utility model adopts is:
Nuclear power plant containment shell machinery penetration piece leak tightness test device
,Comprise gas-holder, suspended body flowmeter, tensimeter and electronic stopclock; L01 one end by the test jointing is connected with blowing plant or gas cylinder with instrument, and the other end of the L01 of test jointing connects the entrance of the valve V01 of compressed air regulating valve; The outlet of the valve V01 of compressed air regulating valve links to each other with the entrance of the valve V02 of stopcock and V03; The joint N01 of the outlet jointing clip formula rapid-acting coupling of the valve V02 of stopcock, after be connected to the entrance of gas-holder; The joint N02 of the outlet jointing clip formula rapid-acting coupling of gas-holder is connected with the entrance of the valve V4 of stopcock afterwards; After the valve V3 of connection stopcock and the outlet of V4 are pooled to a pipeline, branch into two-way and link to each other with the valve V05 of stopcock and the entrance of V07 respectively;
The discharge pipe of stopcock is divided into two, and one is connected with the valve V08 of stopcock, and rear L04 with testing jointing is connected; The joint N03 of another jointing clip formula rapid-acting coupling, behind the connection suspended body flowmeter, the joint N04 of jointing clip formula rapid-acting coupling, pipeline is divided into two afterwards; One is connected with stopcock valve V09, and rear L03 with testing jointing is connected; Another valve V13 with valve V07, V10, V11, V12 and the adjustable safe valve of stopcock is connected; The outlet of the valve V10 of stopcock and Bonding pressure table again after the joint N05 of clamp type quick connector is connected; The L02 of the valve V11 joint test jointing of stopcock; The outlet of the valve V12 of stopcock is connected with adjustable safe valve converges into the test unit that a pipeline and gas discharge outlet are connected in one after the outlet of valve V13 connects.
Outside described employing rapid-acting coupling connected, remaining part all adopted the high-pressure hose pipeline to connect with the mechanical connection form of double card cover.
The described test unit that connects as one is located in the suitcase.
Described suitcase is provided with pulley, pull bar and handle; The length of suitcase is 50cm, the wide 25cm of being, the high 60cm of being.
Be provided be used to the storage area of depositing other aid and high-pressure hose in the described suitcase.
Described test jointing (L01-L04) is the rapid-acting coupling that is threaded that can change; Test jointing (L01-L04) can according to circumstances be adjusted length with the high-pressure hose of equipment connection, and length range is 3 m-15m.
The instrument zone II of described electronic stopclock, tensimeter, suspended body flowmeter assembly can rotate take lower limb as standard shaft 120 degree; The control panel of described instrument zone II is rotary control panel.
The valve V13 of described adjustable safe valve is provided with the relief pressure of safety valve; Described gas discharge outlet is taked the method for hemispheric discharging, and the flow attack that guarantees gas is unlikely to cause the injury of personnel and equipment, by the value of the Calculation of Gas amount that obtains, determines the erasure effect of quieter.
One side of described suspended body flowmeter is provided with O type circle.
Described O type circle is that internal diameter is 8mm, and the sealing hard transparent O type circle of the pure water of volume 60% is housed; The angle that the plane of this O type circle and interface, instrument zone are 45 degree when the instrument zone is rotated, adopts this O type circle to carry out vertical calibration.
The beneficial effects of the utility model are:
The utility model is in conjunction with three kinds of ultimate principles of present Chinese Nuclear Power Stations containment machinery penetration piece impermeability test, the fundamental test equipment that these three kinds of ultimate principles need to be taked carries out choose reasonable and collocation, form a complete apparatus system, test applied widely, the device strong operability.Adopt the form of portable draw-bar box, each parts of test unit are carried out rational distributed combination, reduced the volume of test unit, greatly improved the convenience that device carries.Need the correlate meter of verification to take to carry out the form that clamping hoop type is connected fast with system and device integral body, be convenient to dismounting, make things convenient for instrument verification.
The utlity model has easy to carryly, simple to operate, practical, can greatly reduce running time of test, then reduce experiment operator in the time of radiation control zone, reduce the risk that operating personnel are subject to radiation hazard.
Description of drawings
Below in conjunction with the drawings and specific embodiments the utility model is described in further detail.
Fig. 1 is structure flow chart of the present utility model;
Fig. 2 is structural representation of the present utility model;
Fig. 3 is nuclear power station machinery penetration piece impermeability test connection diagram.
Among Fig. 1: test jointing 1(L01-L04), compressed air regulating valve 2(V01), stopcock 3(V02-V12), clamp type quick connector 4(N01-N05), gas-holder 5, suspended body flowmeter 6, tensimeter 7, adjustable safe valve 8(V13), gas discharge outlet 9, electronic stopclock 10.
Embodiment
The utility model is a kind of nuclear power plant containment shell machinery penetration piece leak tightness test device
,As shown in Figure 1, comprise gas-holder 5, suspended body flowmeter 6, tensimeter 7 and electronic stopclock 10.The other end of the L01 of test jointing 1 connects the entrance of the valve V01 of compressed air regulating valve 2; The outlet of the valve V01 of compressed air regulating valve 2 links to each other with the entrance of the valve V02 of stopcock 3 and V03; The joint N01 of the outlet jointing clip formula rapid-acting coupling 4 of the valve V02 of stopcock 3, after be connected to the entrance of gas-holder 5; The joint N02 of the outlet jointing clip formula rapid-acting coupling 4 of gas-holder 5 is connected with the entrance of the valve V4 of stopcock 3 afterwards; After the valve V3 of connection stopcock 3 and the outlet of V4 are pooled to a pipeline, branch into two-way and link to each other with the valve V05 of stopcock 3 and the entrance of V07 respectively; The discharge pipe of stopcock 3 is divided into two, and one is connected with the valve V08 of stopcock 3, and rear L04 with testing jointing 1 is connected; The joint N03 of another jointing clip formula rapid-acting coupling 4, behind the connection suspended body flowmeter 6, the joint N04 of jointing clip formula rapid-acting coupling 4, pipeline is divided into two afterwards; One is connected with stopcock 3 valve V09, and rear L03 with testing jointing 1 is connected; Another valve V13 with valve V07, V10, V11, V12 and the adjustable safe valve 8 of stopcock 3 is connected; The outlet of the valve V10 of stopcock 3 and Bonding pressure table 7 again after the joint N05 of clamp type quick connector 4 is connected; The L02 of the valve V11 joint test jointing 1 of stopcock 3; After connecting, the outlet of the valve V13 that the outlet of the valve V12 of stopcock 3 is connected with adjustable safe valve converges into the test unit that a pipeline and gas discharge outlet 9 are connected in one.Above-mentioned except employing rapid-acting coupling connects, remaining part equipment all adopts the high-pressure hose pipeline to connect with the mechanical connection form of double card cover.
Among Fig. 1, wherein test jointing 1 and be provided with 4, comprise L01-L04, be the rapid-acting coupling that is threaded that can change, the centre can increase the length of high-pressure hose, and length range is 3 m-15m.The remote source of the gas of convenient connection; The distance of increase and radioactive source reaches the purpose that radiation length protects.The L01 that wherein tests jointing 1 generally is connected with blowing plant or gas cylinder with instrument, and the L02-L04 of test jointing 1 generally is connected with nuclear power plant containment shell machinery penetration piece impermeability test pipeline; The valve of compressed air regulating valve 2 is V01, mainly is the pressure of regulating system; Stopcock 3 is 11, and wherein the V02-V12 in the stopcock 3 mainly is according to different test principles, by setting the on off state of different stopcocks, selects the Instrument connection mode that is fit to.Gas-holder 5 on the utility model test unit, suspended body flowmeter 6, tensimeter 7 links to each other with device, all takes clamp type quick connector 4 to connect, and is convenient to dismounting, verification and the replacing of test-meter; Because the pipeline space of some penetration piece is too little, therefore increase gas-holder 5, purpose is in order to increase the gas storage space of test, to be convenient to test findings and to process.Adopt suspended body flowmeter 6 to measure to need in the process of the test gas supply flow and the leakage flow that record.Employing tensimeter 7 is indicated charge pressure and the change value of pressure in the process of the test.
Adjustable safe valve 8, gas discharge outlet 9 have carried out relevant safe design and have considered.Wherein the valve V13 of adjustable safe valve 8 can arrange the relief pressure of safety valve, prevents the maloperation in process of the test, and makes the test unit superpressure, and the accident of the injury person, infringement equipment occurs.Gas discharge outlet 9 has been considered factor aspect the control two of noise reduction and gas emissions in design process.Wherein the factor of gas emissions is mainly considered both can discharge gas, and gas purging is taked the method for hemispheric discharging simultaneously, and the flow attack of assurance gas is unlikely to cause the injury of personnel and equipment.By the value of the Calculation of Gas amount that obtains, determine the erasure effect design of quieter, not affected by noise to guarantee the staff.
As shown in Figure 2, Fig. 2 is structural representation of the present utility model.This test unit carries easy, easy to operate effect for reaching, and adopts the box one-piece construction of Portable handheld.By all high pressure lines that Fig. 1 is described, the test unit equipment unification that valve and relevant connection are integrated is assemblied in a long mobile device suitcase the inside with pulley, pull bar and handle for 50cm, the wide 25cm of being, the high 60cm of being.Be provided be used to the storage area of depositing other aid and high-pressure hose in the described suitcase.
Fig. 2 has mainly showed and has opened the containment penetration leak tightness test device operation interface topology layout that presents behind the Portable handheld case.As can be seen from Figure 2, this operation interface mainly is divided into 5 parts, is respectively: operation valve zone I is respectively the operating grip of stopcock 3 V10, V13, V08, V09 and compressed air regulating valve 2 V01 from top to bottom.Instrument zone II, this zone mainly comprises electronic stopclock 10: be used for timing and measures ambient temperature; Tensimeter 7 on the spot: the compressed-air actuated pressure that main measuring system is filled with, the adjusting to system pressure of indicating simultaneously compressed air regulating valve 2 V01; Suspended body flowmeter 6 assemblies: comprise suspended body flowmeter 6 and transparent O type circle.Suspended body flowmeter 6 is mainly used in measuring the flow of the gas of supplying with or revealing.For guaranteeing that suspended body flowmeter is in plumbness in working order, whole instrument zone II can rotate take lower limb as standard shaft 120 degree, and the control panel of described instrument zone II is rotary control panel.
The sealing hard transparent O type circle of the pure water that volume 60% is housed that it is 8mm that an internal diameter is installed on the right of suspended body flowmeter 6.The angle that the plane of this O type circle and interface, instrument zone are 45 degree when the instrument zone is rotated, adopts this O type circle to carry out vertical calibration.Operation valve zone III is respectively the operating grip of stopcock 3 V02-V07 from top to bottom.Gas-holder 5 storage area IV.The storage area V of test jointing 1, relevant high-pressure hose and other aid etc.The rapid-acting coupling that is threaded of described test jointing 1 for changing.This device can directly be connected with compressed-air line with instrument, this device can be connected with the mobile source of the gas such as nitrogen pot, increased the scope of application of device.
Should satisfy following requirement during nuclear power plant containment shell machinery penetration piece impermeability test: the pressurized mode is adopted in test, compression aspect must to carry out the pressurized direction of security function when the accident consistent with the test isolation valve, otherwise, the result's equivalence when needing the verification test result consistent with the pressurized direction or more conservative; What telechiric device was installed is tested valve, answers remote closing, must not close by on-site manual; Pressure medium is decided by the fluid of this system and adds water or aerating, in order to reduce the workload of test, generally adopts pressurized air; Test pressure is containment design pressure; When adopting air testing, the liquid of being tested in the pipeline section of valve place must be emptying, avoids the test findings error too large; Test method is divided into discharge method and pressure decline method.
As shown in Figure 3, Fig. 3 is nuclear power station machinery penetration piece impermeability test connection diagram.Wherein valve A, valve B, valve C are the required valve that carries out impermeability test, and valve t1 and valve t2 are the test valve of nuclear power station machinery penetration piece impermeability test.Below in conjunction with Fig. 1 and Fig. 3, according to discharge method and pressure decline method, introduce test connected mode and the using method of nuclear power station machinery penetration piece leak tightness test device.
1, discharge method:
Method 1: namely connected mode 1, and pressurization and connection nuclear power station machinery penetration piece impermeability test are to the upstream of quilt test valve.
As shown in Figure 3, the valve that test is valve A, and the valve that test is opened is valve t1, and the valve of closing is A, valve B, valve C and valve t2.Test interface 1 among Fig. 2 is connected with the test jointing 1L02 rapid-acting coupling of test unit, and the L01 of the test jointing 1 of test unit is connected with compressed air gas source.Open stopcock 3 V04-V06, stopcock 3 V10 and stopcock 3 V11 confirm that simultaneously compressed air regulating valve 2 V01, stopcock 3 V02, stopcock 3 V03, stopcock 3 V07-V09 and V12 close.Slowly regulate compressed air regulating valve 2 V01, in pipeline section between A and B, be pressurized to containment design pressure, after reaching containment design pressure, slowly turns the pressure that makes tensimeter 7 compressed air regulating valve 2 V01 down to keep the duration of test constant pressure, the flow of suspended body flowmeter 6 demonstrations this moment is total slip of valve A and valve B, for the purpose of conservative, can be used as the slip of valve A.Calculate the slip that correction just can be calculated valve A by the slip that obtains and according to the temperature that records on the electronic stopclock.Open stopcock 3V12 after the off-test to system deflation, and recovery device.
Method 2: namely connected mode 2, tested the valve downstream pressurization, and the downstream connects flowmeter.As shown in Figure 3, B is that A, B, C close by the test valve.Open t1 and t2 during test, test jointing 1 L01 is connected to the instrument compressed air source, and test jointing 1 L02 is connected on the t1 valve ozzle, and the L04 of test jointing 1 is connected on the t2 valve ozzle.Open stopcock 3 V04 and stopcock 3 V07-V11, confirm that simultaneously compressed air regulating valve 2 V01, stopcock 3 V02, stopcock 3 V03, stopcock 3V05-V06 and stopcock 3 V12 close.Slowly open compressed air regulating valve 2 V01, be forced into containment design pressure to the pipeline between A, the B, keep the duration of test constant pressure, suspended body flowmeter 6 shows that flow is the slip of B valve.Calculate the slip that correction just can be calculated valve B by the leakage rate that obtains and according to the temperature that records on the electronic stopclock 10.Open stopcock 3 V12 after the off-test to system deflation, and recovery device.
2, pressure decline method: namely connected mode 3.
As shown in Figure 3, C is that the valve of opening during test is t1, t2 by the test valve, and the valve of closing is A, B, C.Open t1 and t2 during test, the L01 of test jointing 1 is connected to the instrument compressed air source, and the L02 of test jointing 1 is connected on the t1 valve ozzle, and the L03 of test jointing 1 is connected on the t2 valve ozzle.Open stopcock 3 V02, stopcock 3 V03, stopcock 3 V07, stopcock 3 V10-V11, confirm that simultaneously compressed air regulating valve 2 V01, stopcock 3 V04-V06, stopcock 3 V08-V09 and stopcock 3 V12 close.Slowly open compressed air regulating valve 2 V01, be forced into containment design pressure to the pipeline between A, the B.After the pressurization of the pipeline between A, the B reached containment design pressure, cut-out tap valve 3 V11 and valve t1 opened stopcock 3 V06 and V09, are gas-holder 5 to pipeline section between A and B, and the demarcation volume is 1768cm3, is pressurized to containment design pressure.Closes compression air control valve 2 V01 and timing, pressure drop after after a while can get leakage rate and the slip of valve C as calculated.Open first stopcock 3 V12 after the off-test, discharge the pressurized air between B and the C, then open the pressurized air between stopcock 3 V11 release A and the B.
Claims (10)
1. nuclear power plant containment shell machinery penetration piece leak tightness test device
,Comprise gas-holder (5), suspended body flowmeter (6), tensimeter (7) and electronic stopclock (10); It is characterized in that:
L01 one end of test jointing (1) is connected with blowing plant or gas cylinder with instrument, and the other end of the L01 of test jointing (1) connects the entrance of the valve V01 of compressed air regulating valve (2); The outlet of the valve V01 of compressed air regulating valve (2) links to each other with the valve V02 of stopcock (3) and the entrance of V03; The joint N01 of the outlet jointing clip formula rapid-acting coupling (4) of the valve V02 of stopcock (3), after be connected to the entrance of gas-holder (5); The joint N02 of the outlet jointing clip formula rapid-acting coupling (4) of gas-holder (5) is connected with the entrance of the valve V4 of stopcock (3) afterwards; After the valve V3 of connection stopcock (3) and the outlet of V4 are pooled to a pipeline, branch into two-way and link to each other with the valve V05 of stopcock (3) and the entrance of V07 respectively;
The discharge pipe of stopcock (3) is divided into two, and the valve V08 with stopcock (3) is connected, and the L04 with test jointing (1) is connected afterwards; The joint N03 of another jointing clip formula rapid-acting coupling (4), behind the connection suspended body flowmeter (6), the joint N04 of jointing clip formula rapid-acting coupling (4), pipeline is divided into two afterwards; One is connected with stopcock (3) valve V09, and rear L03 with testing jointing (1) is connected; Another valve V13 with valve V07, V10, V11, V12 and the adjustable safe valve (8) of stopcock (3) is connected; The outlet of the valve V10 of stopcock (3) and Bonding pressure table (7) again after the joint N05 of clamp type quick connector (4) is connected; The L02 of the valve V11 joint test jointing (1) of stopcock (3); The outlet of the valve V12 of stopcock (3) is connected 8 with adjustable safe valve) the outlet of valve V13 converge into the test unit that a pipeline and gas discharge outlet (9) are connected in one after connecting.
2. nuclear power plant containment shell according to claim 1 machinery penetration piece leak tightness test device, it is characterized in that: outside described employing rapid-acting coupling connected, remaining part all adopted the high-pressure hose pipeline to connect with the mechanical connection form of double card cover.
3. nuclear power plant containment shell according to claim 1 machinery penetration piece leak tightness test device, it is characterized in that: the described test unit that connects as one is located in the suitcase.
4. nuclear power plant containment shell according to claim 3 machinery penetration piece leak tightness test device, it is characterized in that: described suitcase is provided with pulley, pull bar and handle; The length of suitcase is 50cm, the wide 25cm of being, the high 60cm of being.
5. nuclear power plant containment shell machinery penetration piece leak tightness test device according to claim 3 is characterized in that: be provided be used to the storage area of depositing other aid and high-pressure hose in the described suitcase.
6. nuclear power plant containment shell according to claim 1 machinery penetration piece leak tightness test device, it is characterized in that: described test jointing (1) (L01-L04) is the rapid-acting coupling that is threaded that can change; Test jointing (1) (L01-L04) can according to circumstances be adjusted length with the high-pressure hose of equipment connection, and length range is 3 m-15m.
7. nuclear power plant containment shell according to claim 1 machinery penetration piece leak tightness test device, it is characterized in that: the instrument zone II of described electronic stopclock (10), tensimeter (7), suspended body flowmeter (6) assembly can rotate take lower limb as standard shaft 120 and spend; The control panel of described instrument zone II is rotary control panel.
8. nuclear power plant containment shell according to claim 1 machinery penetration piece leak tightness test device, it is characterized in that: the valve V13 of described adjustable safe valve (8) is provided with the relief pressure of safety valve; Described gas discharge outlet (9) is taked the method for hemispheric discharging, and the flow attack that guarantees gas is unlikely to cause the injury of personnel and equipment, by the value of the Calculation of Gas amount that obtains, determines the erasure effect of quieter.
9. nuclear power plant containment shell according to claim 1 machinery penetration piece leak tightness test device is characterized in that: described suspended body flowmeter (6) one side the O type that is provided with circle.
10. nuclear power plant containment shell according to claim 9 machinery penetration piece leak tightness test device, it is characterized in that: described O type circle is that internal diameter is 8mm, and the sealing hard transparent O type circle of the pure water of volume 60% is housed; The angle that the plane of this O type circle and interface, instrument zone are 45 degree when the instrument zone is rotated, adopts this O type circle to carry out vertical calibration.
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| Application Number | Priority Date | Filing Date | Title |
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| CN2012205703917U CN202886079U (en) | 2012-11-01 | 2012-11-01 | Sealing performance test device of mechanical penetration pieces of safety shell in nuclear power station |
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| CN2012205703917U CN202886079U (en) | 2012-11-01 | 2012-11-01 | Sealing performance test device of mechanical penetration pieces of safety shell in nuclear power station |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102928182A (en) * | 2012-11-01 | 2013-02-13 | 辽宁省电力有限公司电力科学研究院 | Leakage test device for mechanical penetration piece of nuclear power plant containment vessel |
| CN114061855A (en) * | 2021-10-22 | 2022-02-18 | 中核核电运行管理有限公司 | Nuclear power plant containment penetration piece sealing test operating system and method |
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2012
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102928182A (en) * | 2012-11-01 | 2013-02-13 | 辽宁省电力有限公司电力科学研究院 | Leakage test device for mechanical penetration piece of nuclear power plant containment vessel |
| CN102928182B (en) * | 2012-11-01 | 2016-02-03 | 辽宁省电力有限公司电力科学研究院 | Leakage test device for mechanical penetration piece of nuclear power plant containment vessel |
| CN114061855A (en) * | 2021-10-22 | 2022-02-18 | 中核核电运行管理有限公司 | Nuclear power plant containment penetration piece sealing test operating system and method |
| CN114061855B (en) * | 2021-10-22 | 2024-01-12 | 中核核电运行管理有限公司 | Nuclear power plant containment penetration piece tightness test operation system and method |
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