CN202018832U - Test device for loss of coolant accident (LOCA) of nuclear power station - Google Patents
Test device for loss of coolant accident (LOCA) of nuclear power station Download PDFInfo
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- CN202018832U CN202018832U CN2011201151231U CN201120115123U CN202018832U CN 202018832 U CN202018832 U CN 202018832U CN 2011201151231 U CN2011201151231 U CN 2011201151231U CN 201120115123 U CN201120115123 U CN 201120115123U CN 202018832 U CN202018832 U CN 202018832U
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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
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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 test device for the loss of coolant accident (LOCA) of a nuclear power station. The device comprises a test cabin, a current regulator, a voltage regulator, an over-heat steam boiler, a compressed air storage tank and two steam storage tanks, wherein the test cabin can contain a tested sample; the current regulator and the voltage regulator are connected with the tested sample; the over-heat steam boiler is connected with the two steam storage tanks; the two steam storage tanks are connected with the test cabin by a plurality of steam pipelines respectively; and the compressed air storage tank is connected with the test cabin by an air pipeline. In the test device for the LOCA of the nuclear power station, the highest steam temperature of the test cabin can reach 280 DEG C, the highest steam pressure can reach 0.80 MPa, and a peak value temperature is raised from 50 DEG C to 141 DEG C within 1 second, so requirements on LOCA test of an advanced passive (AP) 1000 nuclear power station are completely met.
Description
Technical field
The utility model relates to a kind of nuclear power station LOCA test unit, particularly a kind of nuclear power station LOCA test unit that satisfies AP1000 nuclear power station LOCA testing requirements.
Background technology
Because the heap type difference of nuclear power plant reactor, so the enveloping curve of LOCA test (test of forfeiture cooling medium accident) is also different.Be mainly reflected in: 1) the highest vapor (steam) temperature; 2) vapor pressure; 3) peak temperature ascending velocity; Rate of pressure rise when 4) peak temperature rises; 5) the peak temperature retention time; Temperature and pressure retention time when 6) chemical mediator sprays etc.Wherein the highest vapor (steam) temperature, vapor pressure and peak temperature ascending velocity are the gordian techniquies of nuclear power station loss of-coolant accident (LOCA) LOCA test.
AP1000 nuclear power station " the DBA enveloping curve in APP-GW-G1-002-AP1000 container Nei Yi district " according to the international state-of-the-art of representative, the highest vapor (steam) temperature is 214 ℃, vapor pressure is 0.40MPa, and the peak temperature ascending velocity is: rises to 141 ℃ from 50 ℃ in the 1s.But traditional in the past LOCA test unit generally the highest vapor (steam) temperature is 156 ℃, vapor pressure is 0.56MPa, the peak temperature ascending velocity is: rise to 156 ℃ from 50 ℃ in the 20s, be the test parameters of typical saturated vapour, can not satisfy the LOCA testing requirements of AP1000 nuclear power station superheated vapor test parameters.
The utility model content
Problem to be solved in the utility model provides a kind of nuclear power station LOCA test unit of the AP1000 of satisfying nuclear power station, overcomes the above-mentioned problems in the prior art.
The utility model nuclear power station LOCA tests transposition, comprise the test cabin that can hold tested sample, and the current regulator and the voltage regulator that can link to each other with tested sample, also comprise superheated steam boiler, compressed air storage tank and vapor storage, superheated steam boiler links to each other with vapor storage, vapor storage links to each other with described test cabin by many steam pipeworks, and described compressed air storage tank links to each other with described test cabin by air pipe line.
Vapor storage described in the utility model has two to be in parallel, and is provided with the branch drum between described superheated steam boiler and two vapor storage.
Test cabin described in the utility model links to each other with vacuum pump.
Be provided with spray head in the test cabin described in the utility model, spray head links to each other with the medium jar, and is provided with recovery tube in the bottom of test cabin, and recovery tube links to each other with drainage.
Be provided with High-temperature Magnetic Pump between medium jar described in the utility model and spray head.
Spray head described in the utility model is provided with the direct traffic device.
Be respectively equipped with solenoid valve on many steam pipeworks described in the utility model and the described air pipe line.
Volume in the vapor storage described in the utility model is greater than the volume of described test cabin.
Vapor storage described in the utility model and steam pipework are equipped with heat-insulation layer.
Compressed air storage tank described in the utility model links to each other with air compressor machine, and described compressed air storage tank also links to each other with two vapor storage by pipeline.
By above technical scheme, nuclear power station LOCA test unit of the present utility model, the highest vapor (steam) temperature of its test cabin can reach 280 ℃, vapor pressure can reach 0.80MPa, rise to greater than 141 ℃ from 50 ℃ in peak temperature ascending velocity: the 1s, satisfy the requirement of AP1000 nuclear power station LOCA test fully.What and openings of sizes of the steam pipework of the vapor (steam) temperature of vapor (steam) temperature that produces by the control superheated steam boiler and pressure, gas-holder and pressure and control turnover test cabin etc. can satisfy the requirement of various heap type nuclear power station LOCA test enveloping curves simultaneously.
Description of drawings
The concrete structure figure of Fig. 1 the utility model nuclear power station LOCA test unit.
Among the figure, 1, superheated steam boiler; 2, vapor storage; 3, vapor storage; 4, divide drum; 5, compressed air storage tank; 6, test cabin; 7, voltage regulator; 8, current regulator; 9, tested sample; 10, air compressor machine; 11, vacuum pump; 12, High-temperature Magnetic Pump; 13, the medium jar; 14, spray head; 15, solenoid valve.
Embodiment
As shown in Figure 1, nuclear power station LOCA test unit of the present utility model, comprise the test cabin 6 that can hold tested sample 9, and current regulator 8 that links to each other with tested sample and voltage regulator 7, also comprise superheated steam boiler 1, compressed air storage tank 5 and two vapor storage 2,3, superheated steam boiler 1 links to each other with two vapor storage 2,3, two vapor storage link to each other with test cabin 6 by many steam pipeworks respectively, and compressed air storage tank 5 links to each other with test cabin 6 by air pipe line.
The utility model adopts 2 tons of superheated steam boilers as test steam source of the gas, and it both can produce the superheated vapor of high heat low, also can produce saturated vapour.Superheated steam boiler 1 links to each other with two vapor storage 2,3 by dividing drum 4, and be provided with solenoid valve in the porch that enters two vapor storage respectively, two vapor storage 2,3 link to each other with test cabin 6 by many steam pipeworks respectively, compressed air storage tank 5 links to each other with test cabin 6 by air hose, and is respectively equipped with solenoid valve 15 on many steam pipeworks and the air pipe line.Employing is implemented fast aeration to test cabin than the vapor storage of the big several times of test cabin 6 useful volumes and compressed air storage tank, and to effective control of vapor (steam) temperature and pressure.
Compressed air storage tank 5 links to each other with air compressor machine 10, provides pressurized air by air compressor machine 10.Compressed air storage tank also links to each other with two vapor storage by pipeline, and this pipeline is provided with solenoid valve.Before tested sample being carried out the LOCA test, earlier fill the compression air to two vapor storage by compressed air storage tank, vapor storage charges into test cabin to those pressurized air again, come pressure in the debugging test storehouse by regulating all solenoid valves, with this preliminary examination before testing, but signal piping whether conducting and inflation rate etc.And at the trial, compressed air storage tank is connected with test cabin, be used for regulating vapor (steam) temperature and pressure in the test cabin.
During test, whether set pipeline by the solenoid valve 15 on the switch turnover gas steam pipework communicates, pipeline quantity can be selected according to testing requirements, wherein two road air inlet pipelines and one road outlet pipe adopt controllable electromagnetic valve control turnover tolerance, one road air pipe line adopts controllable electromagnetic valve control air inflow, thereby implements the accurate control to test cabin vapor (steam) temperature and pressure.And vapor storage and all steam pipeworks are equipped with heat-insulation layer, adopt the heat tracing measure, make the pipeline thermal losses low as far as possible.Adopt the multichannel steam pipework simultaneously test cabin to be implemented fast aeration, the heating rate in warranty test storehouse.
Above-mentioned test cabin 6 links to each other with vacuum pump 11, to test cabin before the steam, with vacuum pump test cabin is evacuated earlier, accelerate the intake velocity of steam in the test cabin with this, the heating rate in warranty test storehouse.
This test unit also can carry out chemical experiment, is provided with spray head 14 in the test cabin 6, and this spray head links to each other with 14 medium jars 13 by High-temperature Magnetic Pump 12, can implement the injection of chemical mediator to tested sample.And the injection flow of employing liquid mass flow meter Long-distance Control chemical mediator; The spray head that adopts high temperature resistant, high pressure resistant and corrosion resistant liquid water pump and possess the direct traffic device is implemented the injection of chemical mediator.And being provided with recovery tube in the bottom of test cabin, recovery tube links to each other with drainage, realizes the recycling of chemical mediator and condensate water in the test cabin.Vapor storage, compressed air storage tank also link to each other with drainage respectively with the medium jar simultaneously.
This test unit selection sampling period is that the data collecting card of 0.1s calculates the vapor (steam) temperature of machine and the signal input of pressure, vapor (steam) temperature and the time dependent curve of pressure in the record utmost point short time as data recording.And be equipped with test current and reach 1000A, trial voltage reaches the energising utility appliance of the testing transformer of 50kV as sample.This test unit can satisfy AP1000 nuclear power station LOCA requirement of experiment, also can satisfy other various heap type nuclear power station LOCA testing requirementss, the highest vapor (steam) temperature of its test cabin can reach 280 ℃, vapor pressure can reach 0.80MPa, rises to greater than 141 ℃ from 50 ℃ in peak temperature ascending velocity: the 1s.And steam pipework that can be by control turnover test cabin what and openings of sizes etc., enforcement is to the accurate control of test cabin vapor (steam) temperature and pressure.
Claims (10)
1. nuclear power station LOCA test unit, comprise the test cabin (6) that can hold tested sample (9), and current regulator (8) that can be electrically connected and voltage regulator (7) with tested sample (9), it is characterized in that, also comprise superheated steam boiler (1), compressed air storage tank (5) and vapor storage (2,3), superheated steam boiler (1) links to each other with vapor storage, vapor storage links to each other with described test cabin (6) by many steam pipeworks, and described compressed air storage tank (5) links to each other with described test cabin (6) by air pipe line.
2. nuclear power station LOCA test unit according to claim 1 is characterized in that described vapor storage has two to be in parallel, and is provided with the branch drum between described superheated steam boiler (1) and two vapor storage (2,3).
3. nuclear power station LOCA test unit according to claim 1 is characterized in that, described test cabin (6) links to each other with vacuum pump (11).
4. nuclear power station LOCA test unit according to claim 1 is characterized in that, is provided with spray head (14) in the described test cabin, and spray head (14) links to each other with medium jar (13), and is provided with recovery tube in the bottom of test cabin, and recovery tube links to each other with drainage.
5. nuclear power station LOCA test unit according to claim 4 is characterized in that, is provided with High-temperature Magnetic Pump (12) between described medium jar (1) and spray head (14).
6. nuclear power station LOCA test unit according to claim 5 is characterized in that described spray head (14) is provided with the direct traffic device.
7. nuclear power station LOCA test unit according to claim 1 is characterized in that, is respectively equipped with solenoid valve (15) on described air pipe line and many steam pipeworks.
8. nuclear power station LOCA test unit according to claim 1 is characterized in that, the volume in the described vapor storage is greater than the volume of described test cabin.
9. nuclear power station LOCA test unit according to claim 1 is characterized in that described vapor storage and steam pipework are equipped with heat-insulation layer.
10. nuclear power station LOCA test unit according to claim 1 is characterized in that, described compressed air storage tank (5) links to each other with air compressor machine (10), and described compressed air storage tank (5) also links to each other with two vapor storage (2,3) by pipeline.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2011201151231U CN202018832U (en) | 2011-04-19 | 2011-04-19 | Test device for loss of coolant accident (LOCA) of nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2011201151231U CN202018832U (en) | 2011-04-19 | 2011-04-19 | Test device for loss of coolant accident (LOCA) of nuclear power station |
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| Publication Number | Publication Date |
|---|---|
| CN202018832U true CN202018832U (en) | 2011-10-26 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN2011201151231U Expired - Lifetime CN202018832U (en) | 2011-04-19 | 2011-04-19 | Test device for loss of coolant accident (LOCA) of nuclear power station |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104269196A (en) * | 2014-08-27 | 2015-01-07 | 上海发电设备成套设计研究院 | Device and method for carrying out tests for stimulating environment in high energy pipeline rupture accident in nuclear power plant |
| CN106328227A (en) * | 2016-10-18 | 2017-01-11 | 中广核研究院有限公司 | Spray test device and method for containment vessel |
| CN108257691A (en) * | 2016-12-29 | 2018-07-06 | 福建福清核电有限公司 | It is a kind of to study the device that large break accident influences containment in station blackout and shell |
| CN112768097A (en) * | 2020-12-22 | 2021-05-07 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Nuclear detector testing device |
-
2011
- 2011-04-19 CN CN2011201151231U patent/CN202018832U/en not_active Expired - Lifetime
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104269196A (en) * | 2014-08-27 | 2015-01-07 | 上海发电设备成套设计研究院 | Device and method for carrying out tests for stimulating environment in high energy pipeline rupture accident in nuclear power plant |
| CN106328227A (en) * | 2016-10-18 | 2017-01-11 | 中广核研究院有限公司 | Spray test device and method for containment vessel |
| CN108257691A (en) * | 2016-12-29 | 2018-07-06 | 福建福清核电有限公司 | It is a kind of to study the device that large break accident influences containment in station blackout and shell |
| CN108257691B (en) * | 2016-12-29 | 2020-01-03 | 福建福清核电有限公司 | Device for researching influence of power failure of whole plant and large-break accident in shell on containment |
| CN112768097A (en) * | 2020-12-22 | 2021-05-07 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Nuclear detector testing device |
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Legal Events
| Date | Code | Title | Description |
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| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| C41 | Transfer of patent application or patent right or utility model | ||
| TR01 | Transfer of patent right |
Effective date of registration: 20160418 Address after: 200093 Shanghai military road, Yangpu District, No. 1000 Patentee after: SHANGHAI ELECTRIC CABLE Research Institute Patentee after: SHANGHAI NATIONAL CENTER OF TESTING AND INSPECTION FOR ELECTRIC CABLE AND WIRE CO.,LTD. Address before: 200093 Shanghai military road, Yangpu District, No. 1000 Patentee before: Shanghai Electric Cable Research Institute |
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| CP01 | Change in the name or title of a patent holder | ||
| CP01 | Change in the name or title of a patent holder |
Address after: 200093 No. 1000, military road, Shanghai, Yangpu District Patentee after: SHANGHAI ELECTRIC CABLE RESEARCH INSTITUTE Co.,Ltd. Patentee after: Shanghai Guoxian Testing Co.,Ltd. Address before: 200093 No. 1000, military road, Shanghai, Yangpu District Patentee before: SHANGHAI ELECTRIC CABLE Research Institute Patentee before: SHANGHAI NATIONAL CENTER OF TESTING AND INSPECTION FOR ELECTRIC CABLE AND WIRE Co.,Ltd. |
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| TR01 | Transfer of patent right | ||
| TR01 | Transfer of patent right |
Effective date of registration: 20210125 Address after: Room 101, 558 Shanlian Road, Baoshan District, Shanghai, 2004 Patentee after: Shanghai Guoxian Testing Co.,Ltd. Address before: 200093 No. 1000, military road, Shanghai, Yangpu District Patentee before: SHANGHAI ELECTRIC CABLE RESEARCH INSTITUTE Co.,Ltd. Patentee before: Shanghai Guoxian Testing Co.,Ltd. |
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| CX01 | Expiry of patent term | ||
| CX01 | Expiry of patent term |
Granted publication date: 20111026 |