CN102928182B - Leakage test device for mechanical penetration piece of nuclear power plant containment vessel - Google Patents
Leakage test device for mechanical penetration piece of nuclear power plant containment vessel Download PDFInfo
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- CN102928182B CN102928182B CN201210430116.XA CN201210430116A CN102928182B CN 102928182 B CN102928182 B CN 102928182B CN 201210430116 A CN201210430116 A CN 201210430116A CN 102928182 B CN102928182 B CN 102928182B
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- 238000012360 testing method Methods 0.000 title claims abstract description 133
- 230000035515 penetration Effects 0.000 title claims abstract description 37
- 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
- 230000001105 regulatory effect Effects 0.000 claims description 19
- 238000000034 method Methods 0.000 claims description 16
- 208000027418 Wounds and injury Diseases 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
- 238000007789 sealing Methods 0.000 claims description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 4
- 210000003141 lower extremity Anatomy 0.000 claims description 3
- 230000005855 radiation Effects 0.000 abstract description 8
- 238000012795 verification Methods 0.000 abstract description 5
- 238000002955 isolation Methods 0.000 abstract description 3
- 238000002474 experimental method Methods 0.000 abstract description 2
- 239000007789 gas Substances 0.000 description 23
- 238000013461 design Methods 0.000 description 9
- 230000008569 process Effects 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
- 238000000151 deposition Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 238000011084 recovery Methods 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000008859 change 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
- 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 present invention relates to one and carry out leakage test device for mechanical penetration piece of nuclear power plant containment vessel, for carrying out nuclear power plant containment shell machinery penetration piece isolation valve leak rate test.The present invention is in conjunction with three kinds of ultimate principles of current Chinese Nuclear Power Stations containment machinery penetration piece impermeability test, the fundamental test equipment taked is needed to carry out choose reasonable and collocation these three kinds of ultimate principles, form a complete apparatus system, test applied widely, device strong operability.Adopt the form of portable draw-bar box, each parts of test unit are carried out reasonable layout combination, and volume is little, is easy to carry.Need the correlate meter of verification to take the form of carrying out clamping hoop type being fast connected overall with system and device, be convenient to dismounting, facilitate instrument verification.Have easy to carry, simple to operate, practical, the running time of test can be greatly reduced, then reduce experiment operator in the time of radiation control zone, reduce the risk that operating personnel are subject to radiation hazard.
Description
Technical field
The present invention relates to one and carry out leakage test device for mechanical penetration piece of nuclear power plant containment vessel, 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 radioactive shield function, in things such as primary Ioops large break and secondary circuit vapour line large breaks
Therefore ensure its sealing under operating mode, prevent radiomaterial to be discharged in environment, protection staff and public security.The pipeline of turnover containment should be able to be isolated, to ensure the integrality of containment in above-mentioned accident.Is isolating door generally outside containment, and inner side is isolating door or non-return flap.
For ensureing the tightness of this valve, nuclear power station staff needs regularly to carry out impermeability test to this valve, is nuclear power plant containment shell machinery penetration piece impermeability test.But because the type of the nuclear power station of current China is various, 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 is all take interim test unit.This makes nuclear power station staff before carrying out nuclear power plant containment shell machinery penetration piece impermeability test, all will reselect and apparatus for assembling.This not only needs the test unit of related personnel to each assembling to carry out the inspections such as relevant impermeability, all take different facilities owing to testing at every turn simultaneously, also have great impact for the repeatability of test and the comparability of result, the accuracy of test findings is also often under suspicion.Simultaneously, current domestic nuclear power carries out nuclear power plant containment shell machinery penetration piece impermeability test and adopts interim trial apparatus structure loose, not portable, operate also very inconvenient, this adds test clerk carries out test operation time at reactor building greatly, add testing crew radiation control zone hold-up time and be subject to radiation risk.
Summary of the invention
In order to overcome current leakage test device for mechanical penetration piece of nuclear power plant containment vessel various, loosely organized, not portable and operation inconvenience etc. problem, the present invention, according to nuclear power plant containment shell general at present machinery penetration piece impermeability test principle, provides a kind of leakage test device for mechanical penetration piece of nuclear power plant containment vessel.This device not only structural member gathers, easy to use, and be applicable to current all nuclear power plant containment shell machinery penetration piece impermeability tests, the repeatability of test also strengthens greatly, the running time of test also can shorten, greatly reduce the hold-up time at radiation area of test operation personnel, enhance radiated time protection, reduce the risk that staff is subject to radiant quantity.
The technical solution adopted for the present invention to solve the technical problems is:
Leakage test device for mechanical penetration piece of nuclear power plant containment vessel
,comprise gas-holder, suspended body flowmeter, tensimeter and electronic stopclock: be connected with compressed air for instrument device or gas cylinder by L01 one end of test jointing, 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 is connected with the entrance of valve V02 with V03 of stopcock; 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 V04 of stopcock afterwards; After the outlet of valve V03 and V04 connecting stopcock is pooled to a pipeline, branches into two-way and be connected with the entrance of valve V05 with V07 of stopcock respectively;
The discharge pipe of stopcock is divided into two, and one is connected with the valve V08 of stopcock, is connected afterwards with the L04 of test jointing; The joint N03 of another jointing clip formula rapid-acting coupling, connects after suspended body flowmeter, the joint N04 of jointing clip formula rapid-acting coupling, rear line be divided into two; One is connected with stopcock valve V09, is connected afterwards with the L03 of test jointing; Another is connected with valve V07, V10, V11, V12 of stopcock and the valve V13 of adjustable safe valve; The outlet of the valve V10 of stopcock Bonding pressure table again after being connected with the joint N05 of clamp type quick connector; The L02 of the valve V11 joint test jointing of stopcock; The test unit that a pipeline and gas discharge outlet are connected in one is converged into after the outlet of the valve V12 of stopcock being connected with the outlet of the valve V13 of adjustable safe valve.
Outside described employing rapid-acting coupling connects, the mechanical connection form that remaining part all adopts high-pressure hose pipeline to overlap with double card connects.
The described test unit connected as one is located in suitcase.
Described suitcase is provided with pulley, pull bar and handle; The length of suitcase is 50cm, the wide 25cm of being, height are 60cm.
The storage area for depositing other aid and high-pressure hose is provided with in described suitcase.
Described test jointing (L01-L04), for carrying out the rapid-acting coupling be threaded changed; Test jointing (L01-L04) according to circumstances can adjust length with the high-pressure hose of equipment connection, and length range is 3m-15m.
The instrument region II of described electronic stopclock, tensimeter, suspended body flowmeter assembly can be that standard shaft rotates 120 degree with lower limb; The control panel of described instrument region II is rotary control panel.
The valve V13 of described adjustable safe valve is provided with the relief pressure of safety valve; The method that described gas discharge outlet takes hemispheric to discharge, ensures that the flow attack of gas is unlikely to the injury causing personnel and equipment, by the value of calculating gas flow obtained, determines the erasure effect of quieter.
Described suspended body flowmeter while be provided with O type circle.
Described O type circle is internal diameter is 8mm, and the sealing hard transparent O type circle of the pure water of volume 60% is housed; The plane of this O type circle and instrument region interface are the angle of 45 degree, when instrument region rotates, adopt this O type circle to carry out vertical calibration.
The invention has the beneficial effects as follows:
The present invention is in conjunction with three kinds of ultimate principles of current Chinese Nuclear Power Stations containment machinery penetration piece impermeability test, the fundamental test equipment taked is needed to carry out choose reasonable and collocation these three kinds of ultimate principles, form a complete apparatus system, test applied widely, device strong operability.Adopt the form of portable draw-bar box, each parts of test unit are carried out rational distributed combination, reduces the volume of test unit, substantially increase the convenience that device carries.Need the correlate meter of verification to take the form of carrying out clamping hoop type being fast connected overall with system and device, be convenient to dismounting, facilitate instrument verification.
The present invention has easy to carry, simple to operate, practical, can greatly reduce the running time of test, then reduces experiment operator in the time of radiation control zone, reduces the risk that operating personnel are subject to radiation hazard.
Accompanying drawing explanation
Below in conjunction with the drawings and specific embodiments, the present invention is further detailed explanation.
Fig. 1 is structure flow chart of the present invention;
Fig. 2 is structural representation of the present invention;
Fig. 3 is nuclear power station machinery penetration piece impermeability test connection diagram.
In Fig. 1: test jointing 1(L01-L04), compressed air regulating valve 2(V01), stopcock 3(V02-V12) and, clamp type quick connector 4(N01-N05), gas-holder 5, suspended body flowmeter 6, tensimeter 7, adjustable safe valve 8(V13) and, gas is arranged
Put mouth 9, electronic stopclock 10.
Embodiment
The present invention is a kind of leakage test device for mechanical penetration piece of nuclear power plant containment vessel
,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 is connected with the entrance of valve V02 with V03 of stopcock 3; 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 V04 of stopcock 3 afterwards; After the outlet of valve V03 and V04 connecting stopcock 3 is pooled to a pipeline, branches into two-way and be connected with the entrance of valve V05 with V07 of stopcock 3 respectively; The discharge pipe of stopcock 3 is divided into two, and one is connected with the valve V08 of stopcock 3, is connected afterwards with the L04 of test jointing 1; The joint N03 of another jointing clip formula rapid-acting coupling 4, connects after suspended body flowmeter 6, the joint N04 of jointing clip formula rapid-acting coupling 4, rear line be divided into two; One is connected with stopcock 3 valve V09, is connected afterwards with the L03 of test jointing 1; Another is connected with valve V07, V10, V11, V12 of stopcock 3 and the valve V13 of adjustable safe valve 8; The outlet of the valve V10 of stopcock 3 Bonding pressure table 7 again after being connected with the joint N05 of clamp type quick connector 4; The L02 of the valve V11 joint test jointing 1 of stopcock 3; The test unit that a pipeline and gas discharge outlet 9 are connected in one is converged into after the outlet of the valve V12 of stopcock 3 being connected with the outlet of the valve V13 of adjustable safe valve 8.Above-mentioned except employing rapid-acting coupling connects, the mechanical connection form that remaining part equipment all adopts high-pressure hose pipeline to overlap with double card connects.
In Fig. 1, wherein test jointing 1 and be provided with 4, comprise L01-L04, for carrying out the rapid-acting coupling be threaded changed, centre can increase the length of high-pressure hose, and length range is 3m-15m.The remote source of the gas of convenient connection; Increase the distance with radioactive source, reach the object of radiation length protection.The L01 wherein testing jointing 1 is generally connected with compressed air for instrument device or gas cylinder, and the L02-L04 of test jointing 1 is generally connected with nuclear power plant containment shell machinery penetration piece impermeability test pipeline; The valve of compressed air regulating valve 2 is V01, the mainly pressure of regulating system; Stopcock 3 is 11, and the V02-V12 wherein in stopcock 3, mainly according to different test principles, by setting the on off state of different stopcocks, selects the Instrument connection mode be applicable to.Gas-holder 5 on test unit of the present invention, suspended body flowmeter 6, tensimeter 7 is connected with device, all takes clamp type quick connector 4 to connect, and is convenient to the dismounting of test-meter, School Affairs is changed; Because the pipeline space of some penetration piece is too little, therefore increase gas-holder 5, object is the gas storage space in order to increase test, is convenient to test findings process.Employing suspended body flowmeter 6 measures in process of the test the gas supply flow and leakage flow that need to record.Tensimeter 7 is adopted to indicate charge pressure in process of the test and change value of pressure.
Adjustable safe valve 8, the safe design that gas discharge outlet 9 is correlated with is 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 test unit superpressure, and the accident of the injury person, infringement equipment occurs.Gas discharge outlet 9 considers the control two aspect factor of noise reduction and gas emissions in the design process.Wherein the factor of gas emissions is mainly considered both can discharge gas, simultaneously the gas purging method of taking hemispheric discharge, and the flow attack of guarantee gas is unlikely to the injury causing personnel and equipment.By the value of calculating gas flow obtained, determine the erasure effect design of quieter, to ensure that staff is not affected by noise.
Electronic stopclock 10 possesses monitoring of environmental temperature function simultaneously, so that the time of carrying out timing and the measurement to environment temperature.Except gas-holder 5, suspended body flowmeter 6, outside tensimeter 7, all the other all adopt high-pressure hose, the test jointing 1(L01-L04 of the mode join dependency utilizing double card to overlap), compressed air regulating valve 2(V01), (V02-V12) in stopcock 3, clamp type quick connector 4(N01-N05), adjustable safe valve 8, testing equipment such as gas discharge outlet 9 grade.Adopt high-pressure hose, add the compactedness of the security of system, the convenience of installation and equipment itself; Adopt the connected mode of double card cover, ensure that the impermeability of equipment.
As shown in Figure 2, Fig. 2 is structural representation of the present invention.This test unit carries easy, easy to operate effect for reaching, and adopts the one-piece construction that Portable handheld is box.By all high pressure lines that Fig. 1 is described, test unit equipment that valve and relevant connection are integrated is unified be assemblied in one long for 50cm, wide for 25cm, high for 60cm with inside the mobile device suitcase of pulley, pull bar and handle.The storage area for depositing other aid and high-pressure hose is provided with in described suitcase.
The containment penetration leak tightness test device operation interface topology layout presented after Fig. 2 main presentation opens Portable handheld case.As can be seen from Figure 2, this operation interface is mainly divided into 5 parts, respectively: operation valve region I, is the operating grip of stopcock 3V10, V13, V08, V09 and compressed air regulating valve 2V01 from top to bottom respectively.Instrument region II, this region mainly comprises electronic stopclock 10: for timing and measures ambient temperature; Tensimeter 7 on the spot: the compressed-air actuated pressure that main measuring system is filled with, indicates the adjustment to system pressure of compressed air regulating valve 2V01 simultaneously; Suspended body flowmeter 6 assembly: comprise suspended body flowmeter 6 and transparent O type circle.Suspended body flowmeter 6 is mainly used in the flow of the gas measuring supply or leakage.For ensureing that suspended body flowmeter is in plumbness in working order, whole instrument region II can be that standard shaft rotates 120 degree with lower limb, and the control panel of described instrument region II is rotary control panel.
The sealing hard transparent O type circle that the pure water of volume 60% is housed that an internal diameter is 8mm is installed on the right of suspended body flowmeter 6.The plane of this O type circle and instrument region interface are the angle of 45 degree, when instrument region rotates, adopt this O type circle to carry out vertical calibration.Operation valve region III is the operating grip of stopcock 3V02-V07 from top to bottom respectively.Gas-holder 5 storage area IV.The storage area V of test jointing 1, associated high voltage flexible pipe and other aid etc.Described test jointing 1 is the rapid-acting coupling be threaded can carrying out changing.Not only make this device directly be connected with compressed air for instrument pipeline, also make this device can be connected with mobile sources of the gas such as nitrogen pots, add the scope of application of device.
Following requirement should be met: test adopts pressurized mode during nuclear power plant containment shell machinery penetration piece impermeability test, compression aspect must to perform the pressurized direction of security function when accident consistent with test isolation valve, otherwise, the result equivalence or more conservative when needing verification test result consistent with pressurized direction; That installs telechiric device is tested valve, answers remote closing, must not close by on-site manual; Pressure medium is decided to add water or aerating by the fluid of this system, in order to reduce the workload of test, generally adopts pressurized air; Test pressure is containment design pressure; When adopting air testing, must be emptying by the liquid in the pipeline section of test valve place, avoid 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 for required for carry out the valve of impermeability test, valve t1 and valve t2 is 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: i.e. connected mode 1, pressurization and connection nuclear power station machinery penetration piece impermeability test are to being tested the upstream of 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 closedown is A, valve B, valve C and valve t2.Be connected with the test jointing 1L02 rapid-acting coupling of test unit by test interface 1 in Fig. 2, the L01 of the test jointing 1 of test unit is connected with compressed air gas source.Open stopcock 3V04-V06, stopcock 3V10 and stopcock 3V11, confirm that compressed air regulating valve 2V01, stopcock 3V02, stopcock 3V03, stopcock 3V07-V09 and V12 close simultaneously.Slow adjustment compressed air regulating valve 2V01, containment design pressure is pressurized in pipeline section between A and B, compressed air regulating valve 2V01 is slowly turned down to keep duration of test constant pressure after making the pressure of tensimeter 7 reach containment design pressure, the flow that now suspended body flowmeter 6 shows is total slip of valve A and valve B, for the purpose of conservative, can be used as the slip of valve A.Carry out calculating the slip revised and just can calculate valve A by the slip that obtains and according to the temperature that electronic stopclock records.Stopcock 3V12 be opened to system deflation after off-test, and recovery device.
Method 2: i.e. connected mode 2, pressurizeed by test valve downstream, downstream connects flowmeter.As shown in Figure 3, B is that A, B, C close by test valve.Open t1 and t2 during test, test jointing 1L01 is connected to compressed air for instrument source, and test jointing 1L02 is connected on t1 valve ozzle, and the L04 of test jointing 1 is connected on t2 valve ozzle.Open stopcock 3V04 and stopcock 3V07-V11, confirm that compressed air regulating valve 2V01, stopcock 3V02, stopcock 3V03, stopcock 3V05-V06 and stopcock 3V12 close simultaneously.Slowly open compressed air regulating valve 2V01, be forced into containment design pressure to the pipeline between A, B, keep duration of test constant pressure, suspended body flowmeter 6 shows the slip that flow is B valve.Carry out calculating the slip revised and just can calculate valve B by the leakage rate that obtains and according to the temperature that electronic stopclock 10 records.Stopcock 3V12 be opened to system deflation after off-test, and recovery device.
2, pressure decline method: i.e. connected mode 3.
As shown in Figure 3, C is that the valve opened during test is t1, t2, and the valve of closedown is A, B, C by test valve.Open t1 and t2 during test, the L01 of test jointing 1 is connected to compressed air for instrument source, and the L02 of test jointing 1 is connected on t1 valve ozzle, and the L03 of test jointing 1 is connected on t2 valve ozzle.Open stopcock 3V02, stopcock 3V03, stopcock 3V07, stopcock 3V10-V11, confirm that compressed air regulating valve 2V01, stopcock 3V04-V06, stopcock 3V08-V09 and stopcock 3V12 close simultaneously.Slowly open compressed air regulating valve 2V01, be forced into containment design pressure to the pipeline between A, B.After pipeline pressurization between A, B reaches containment design pressure, cut-out tap valve 3V11 and valve t1, opens stopcock 3V06 and V09, and to pipeline section and gas-holder 5 between A and B, demarcation volume is 1768cm3, is pressurized to containment design pressure.Closes compression air control valve 2V01 timing, through measuring Pressure Drop after a period of time, can obtain leakage rate and the slip of valve C as calculated.First open stopcock 3V12 after off-test, the pressurized air between release B and C, then open the pressurized air between stopcock 3V11 release A and B.
Claims (9)
1. leakage test device for mechanical penetration piece of nuclear power plant containment vessel
,comprise gas-holder (5), suspended body flowmeter (6), tensimeter (7) and electronic stopclock (10); It is characterized in that:
Test jointing (1) L01 one end is connected with compressed air for instrument device or gas cylinder, and the other end of test jointing (1) L01 connects the entrance of compressed air regulating valve (2) V01; The outlet of compressed air regulating valve (2) V01 is connected with the entrance of stopcock (3) V03 with stopcock (3) V02; Outlet jointing clip formula rapid-acting coupling (4) N01 of stopcock (3) V02, after be connected to the entrance of gas-holder (5); Outlet jointing clip formula rapid-acting coupling (4) N02 of gas-holder (5), is connected with the entrance of stopcock (3) V04 afterwards; Connect after the outlet of stopcock (3) V03 and stopcock (3) V04 is pooled to a pipeline, branch into two-way and be connected with the entrance of stopcock (3) V07 with stopcock (3) V05 respectively;
The discharge pipe of stopcock (3) V05 is divided into two, and one is connected with stopcock (3) V08, is connected afterwards with test jointing (1) L04; Another jointing clip formula rapid-acting coupling (4) N03, after connecting suspended body flowmeter (6), jointing clip formula rapid-acting coupling (4) N04, rear line be divided into two; One is connected with stopcock (3) V09, is connected afterwards with test jointing (1) L03; Another is connected with stopcock (3) V07, stopcock (3) V10, stopcock (3) V11, stopcock (3) V12 and adjustable safe valve (8) V13; Bonding pressure table (7) again after the outlet of stopcock (3) V10 is connected with clamp type quick connector (4) N05; Stopcock (3) V11 joint test jointing (1) L02; The test unit that a pipeline and gas discharge outlet (9) are connected in one is converged into after the outlet of stopcock (3) V12 being connected with the outlet of adjustable safe valve (8) V13.
2. leakage test device for mechanical penetration piece of nuclear power plant containment vessel according to claim 1, is characterized in that: described
Outside employing rapid-acting coupling connects, the mechanical connection form that remaining part all adopts high-pressure hose pipeline to overlap with double card connects.
3. leakage test device for mechanical penetration piece of nuclear power plant containment vessel according to claim 1, is characterized in that: the described test unit connected as one is located in suitcase.
4. leakage test device for mechanical penetration piece of nuclear power plant containment vessel according to claim 3, 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, height are 60cm.
5. leakage test device for mechanical penetration piece of nuclear power plant containment vessel according to claim 1, is characterized in that: described test jointing (1) L01-L04, for carrying out the rapid-acting coupling be threaded changed; The high-pressure hose of test jointing (1) L01-L04 and equipment connection according to circumstances can adjust length, and length range is 3m-15m.
6. leakage test device for mechanical penetration piece of nuclear power plant containment vessel according to claim 1, is characterized in that: the instrument region II of described electronic stopclock (10), tensimeter (7), suspended body flowmeter (6) assembly can be that standard shaft rotates 120 degree with lower limb; The control panel of described instrument region II is rotary control panel.
7. leakage test device for mechanical penetration piece of nuclear power plant containment vessel according to claim 1, is characterized in that: described adjustable safe valve (8) V13 is provided with the relief pressure of safety valve; The method that described gas discharge outlet (9) takes hemispheric to discharge, ensures that the flow attack of gas is unlikely to the injury causing personnel and equipment, by the value of calculating gas flow obtained, determines the erasure effect of quieter.
8. leakage test device for mechanical penetration piece of nuclear power plant containment vessel according to claim 1, is characterized in that: the O type that the is provided with circle of described suspended body flowmeter (6).
9. leakage test device for mechanical penetration piece of nuclear power plant containment vessel according to claim 8, is characterized in that: described O type circle is internal diameter is 8mm, and the sealing hard transparent O type circle of the pure water of volume 60% is housed; The plane of this O type circle and instrument region interface are the angle of 45 degree, when instrument region rotates, adopt this O type circle to carry out vertical calibration.
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN103175658B (en) * | 2013-03-05 | 2015-09-30 | 中国核电工程有限公司 | The test method of nuclear power station pipeline leakage rate and system |
| CN105892515A (en) * | 2016-05-25 | 2016-08-24 | 国核工程有限公司 | Safety shell test pressure control system and control method thereof |
| CN106057258B (en) * | 2016-05-30 | 2017-12-05 | 中广核工程有限公司 | Nuclear power station electrical penetration pressure gauge on-line metering method and its pressure monitoring device |
| CN108731872A (en) * | 2017-11-15 | 2018-11-02 | 江苏核电有限公司 | A kind of nuclear power plant containment shell seal tightness test device for pressure measurement |
| CN110444299B (en) * | 2019-07-17 | 2021-05-07 | 中广核工程有限公司 | Nuclear power plant double-layer containment vessel equipment sealed cabin and opening and closing method thereof |
| JP7096802B2 (en) * | 2019-08-28 | 2022-07-06 | 日立Ｇｅニュークリア・エナジー株式会社 | How to manage radioactive material storage containers |
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