CN102194535A - Pre-service hydrostatic test integrated system on secondary side of steam generator - Google Patents
Pre-service hydrostatic test integrated system on secondary side of steam generator Download PDFInfo
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- CN102194535A CN102194535A CN2010101304928A CN201010130492A CN102194535A CN 102194535 A CN102194535 A CN 102194535A CN 2010101304928 A CN2010101304928 A CN 2010101304928A CN 201010130492 A CN201010130492 A CN 201010130492A CN 102194535 A CN102194535 A CN 102194535A
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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
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- 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 invention belongs to the field of pressurized water reactor nuclear power plants, particularly disclosing a pre-service hydrostatic test integrated system on a secondary side of a steam generator of the pressurized water reactor nuclear power plant. The system comprises a pressurizing pump capable of pressurizing to the secondary side of the steam generator, an electric heating water tank and a circulating pump, wherein the pressurizing pump is connected with the circulating pump in parallel; both an inlet of the pressurizing pump and a suction port of the circulating pump are communicated with a water tank outlet pipe of the electric heating water tank; both an outlet of the pressurizing pump and an outlet of the circulating pump are communicated with a hand hole temporary port on the secondary side of the steam generator; and a water tank water return pipe of the electric heating water tank is communicated with a high-position temporary port on the secondary side of the steam generator. The system has stable and reliable performance, can realize uniform and rapid temperature rise of a shell on the secondary side of the steam generator, can be safely and stably pressurized and unpressurized during pressurizing test, and has a small size and high safety, stability and adjusting accuracy; test period can be effectively shortened; and efficiency can be increased.
Description
Technical field
The invention belongs to PWR nuclear power plant (pressurized-water reactor nuclear power plant) field, be specifically related to a kind of preceding hydraulic testing integrated system of steam generator secondary side labour that is applied to PWR nuclear power plant (station).
Background technology
The hydraulic testing is important node and the milestone in the PWR nuclear power plant nuclear island equipment erection schedule before the steam generator secondary side labour.Its scope has covered steam generator secondary side and relative system (comprising main feed system, auxiliary feedwater system, main steam system, drainage or the like) pipeline and isolation boundary one valve.This test comprises that steam generator shell heats up, multinomial technological processes such as steam generator secondary side is boosted, pressurize, release, and is boosting, will realize in the stress-relief process the accurate control to buck speed.
The hydraulic testing before the steam generator secondary side of the nuclear power station labour in the past all is to provide provisional package system to carry out this test by nuclear power technology support company in the world, and expense is very high.Heating process is realized by modes such as large-scale tank car segmentation heating water fillings; Adopt common separate unit pressuring pump to boost.This temporary system mainly contains following shortcoming: system heats up and causes the test period very long very slowly; The equipment dispersed placement, big, the on-the-spot temporary interface of occupation space volume is more, the equipment installation period is long; Security of system is poor, stability is relatively poor, required test operation personnel are many for interim suppressing of connecting.
Summary of the invention
The object of the present invention is to provide the preceding hydraulic testing integrated system of a kind of steam generator secondary side labour, this system performance is reliable and stable, can realize even, the intensification rapidly of steam generator secondary side housing; Can guarantee in the bulge test that system boosts, the step-down safety and steady; Volume is little, safe, stability is high, degree of regulation is high, can effectively shorten the test period, raises the efficiency.
Realize the technical scheme of the object of the invention: hydraulic testing integrated system before a kind of PWR nuclear power plant steam generator secondary side labour, it comprises the pressuring pump that can suppress in steam generator secondary side, electric heating water tank and ebullator, described pressuring pump is in parallel with ebullator, the inlet of pressuring pump and circulation pump intake all are communicated with the water tank outlet of electric heating water tank, suppress delivery side of pump and outlet of circulating pump and all be communicated with the hand hole temporary interface of steam generator secondary side, the water tank return pipe of electric heating water tank is communicated with the high-order temporary interface of steam generator secondary side.
Be provided with preposition supercharge pump between described electric heating water tank and the pressuring pump.
Described pressuring pump comprises big flow pressuring pump and low discharge pressuring pump, big flow pressuring pump and the parallel connection of low discharge pressuring pump.
Big flow pressuring pump after the described parallel connection and low discharge are suppressed between delivery side of pump and the hand hole temporary interface and are provided with the adjustable pressure reflux.
Be provided with bypass release pipeline between described adjustable pressure reflux and the hand hole temporary interface, be communicated with between bypass release pipeline and the system drainage interface, be provided with two bypass release variable valve in parallel between bypass release pipeline and the system drainage interface.
Also be provided with safety valve release pipeline between described adjustable pressure reflux and the hand hole temporary interface, be communicated with between safety valve release pipeline and the system drainage interface, be provided with spring safety valve between safety valve release pipeline and the system's drainage interface.
Useful technique effect of the present invention is: system of the present invention adopts direct hydronic mode to realize being rapidly heated of steam generator shell.This system adopts the integrated design of modularization, all constituents of this system all can be integrated in the template posture container.Have characteristics such as volume is little, function is complete, degree of regulation is high, security height.On the basis that the hydraulic testing rules that satisfy main equipments such as PWR nuclear power plant steam generator require, can effectively shorten the test period, raise the efficiency.This cover system is stable and reliable for performance, can realize even, the intensification rapidly of steam generator secondary side housing; Can guarantee in several ways in the bulge test that system boosts, the step-down safety and steady; Pilot system relevant interface easy accessibility, isolation boundary favorable sealing property everywhere.This systemic-function is comprehensive, can realize corresponding technological requirement in the different tests stage of the hydraulic testing before the steam generator secondary side labour, has guaranteed that the preceding heating process of the hydraulic testing requires and the boosting of the hydraulic testing, release technological requirement.1 high power density electric heating water tank is set in the system provides thermal source for the heat cycles loop.Steam generator secondary side can directly be filled with cold water (demineralized water), by this circulation heating process system to the heating that circulates of the demineralized water in the steam generator, thereby steam generator shell is heated up.Adopt 1 horizontal high performance centrifugal pump as ebullator, this ebullator frame bottom is provided with the stability requirement of beam integrated system of container when satisfying unit operation.Adopt 1 centrifugal pump of vertical axis as preposition supercharge pump, for the pressuring pump suction inlet provide enough pressure head with guarantee to suppress supply water uniform and stable.By the pressuring pump coupling switchover operation of 2 different flows, the control system rate of rise; By the flow of variable frequency adjustment separate unit pressuring pump, the control system rate of rise; In system, be provided with 1 cover setting valve adjustable suppress reflux, when system suppresses top hole pressure and is higher than setting valve, this is suppressed reflux and opens reflux pipeline automatically, the water under high pressure of pressuring pump outlet is back to the supercharging pump intake, maintains below the set-pressure with the top hole pressure of suppressing that guarantees high precision ascending, descending pressing system; Be arranged in parallel 2 high-precision bypass release variable valve in the release bypass, to regulate bypass flow, speed is pressed in the ascending, descending of accuracy-control system, and this variable valve can realize that the high-precision flow under High Pressure Difference, the transformation difference operating mode regulates, with guarantee to suppress, the accurate control of release flow; The outlet of always suppressing in system is provided with 1 high pressure and suppresses the outlet solenoid valve, can guarantee to suppress the quick switching of pipeline, suppresses function with the crawl of realizing system.Be to guarantee the security of the hydraulic testing, suppress delivery side of pump and system always suppresses the spring safety valve that the exit is provided with different set-pressures, with the security of operation that guarantees equipment and operating personnel's safety at every.
Description of drawings
Fig. 1 is that the structure of hydraulic testing integrated system is formed synoptic diagram before a kind of steam generator secondary side labour provided by the present invention.
Among the figure: 1. steam generator secondary side; 2. steam generator secondary side hand hole temporary interface; 3. the high-order temporary interface of steam generator secondary side; 4. high power density electric heating water tank; 5. ebullator; 6. preposition supercharge pump; 7. big flow pressuring pump; 8 low discharge pressuring pumps; 9. bypass release variable valve; 10. adjustable pressure reflux; 11. suppress the outlet safety valve; 12. suppress the outlet solenoid valve; 13. heating water tank liquid level gauge; 14. system's drainage interface; 15. system water supplement interface; 16. radiator thermometer; 17. water tank outlet temperature meter; 18. water tank return water temperature meter; 19. heat cycles flowmeter; 20. suppress delivery gauge; Export tensimeter on the spot 21. suppress; 22. water tank moisturizing isolation valve; 23. tank drains isolation valve; 24. water tank air release; 25. funnel; 26. the hydrophobic isolation valve of funnel; 27. ebullator reverse flow valve; 28. suppress the suction inlet isolation valve; 29. big flow pressuring pump outlet non-return valve; 30 low discharge pressuring pump outlet non-return valves; 31. suppress the by-pass flow isolation valve; 32. safety valve pipeline isolation valve; 33. pressure gauge isolator valve on the spot; 34. the first circulation heating hose; 35. the second circulation heating hose; 36. high-pressure hose; 37. hand hole temporary interface drain valve; 38. first high pressure isolation valve; 39. second high pressure isolation valve; 40. high-order temporary interface air release; 41. the 3rd high pressure isolation valve; 42. water tank filling pipe; 43. tank drains pipe; 44. water tank outlet; 45 water tank return pipes; 46. gas outlet; 47 low discharge reflux pipelines; 48. high-order temporary interface bleeder pipe; 49. bypass release pipeline; 50. safety valve release pipeline; 51. reflux pipeline.
Embodiment
Below in conjunction with drawings and Examples the present invention is described in further detail.
As shown in Figure 1, hydraulic testing integrated system before a kind of PWR nuclear power plant steam generator secondary side labour, it comprises high power density electric heating water tank 4, ebullator 5, preposition supercharge pump 6, big flow pressuring pump 7, low discharge pressuring pump 8, bypass release variable valve 9, adjustable pressure reflux 10, suppress outlet safety valve 11, suppress outlet solenoid valve 12, heating water tank liquid level gauge 13, system's drainage interface 14, system water supplement interface 15, radiator thermometer 16, water tank outlet temperature meter 17, water tank return water temperature meter 18, heat cycles flowmeter 19, suppress delivery gauge 20, suppress and export tensimeter 21 on the spot, water tank moisturizing isolation valve 22, tank drains isolation valve 23, water tank air release 24, funnel 25, the hydrophobic isolation valve 26 of funnel, ebullator reverse flow valve 27, suppress suction inlet isolation valve 28, big flow pressuring pump outlet non-return valve 29, low discharge pressuring pump outlet non-return valve 30, suppress by-pass flow isolation valve 31, safety valve pipeline isolation valve 32, pressure gauge isolator valve 33 on the spot, the first circulation heating hose 34, the second circulation heating hose 35, high-pressure hose 36, hand hole temporary interface drain valve 37, first high pressure isolation valve 38 that is communicated with steam generator secondary side hand hole temporary interface 2, second high pressure isolation valve 39 that is communicated with steam generator secondary side hand hole temporary interface 2, high-order temporary interface air release 40, the 3rd high pressure isolation valve 41 that is communicated with the high-order temporary interface 3 of steam generator secondary side, low discharge reflux pipeline 47, high-order temporary interface bleeder pipe 48, bypass release pipeline 49 and safety valve release pipeline 50.
As shown in Figure 1, high power density electric heating water tank 4 bottoms are provided with water tank filling pipe 42, tank drains pipe 43, water tank outlet 44 and water tank return pipe 45 respectively.Water tank filling pipe 42 is provided with water tank moisturizing isolation valve 22, and the end that suspends of water tank filling pipe 42 is communicated with system water supplement interface 15.Tank drains pipe 43 is provided with tank drains isolation valve 23.The top of high power density electric heating water tank 4 is provided with gas outlet 46, this gas outlet 46 is provided with water tank air release 24, the outlet of water tank gas outlet 46 is provided with a funnel 25, and the downstream of this funnel 25 is connected with system drainage interface 14 through the hydrophobic isolation valve 26 of funnel.Also be provided with following measurement instrument on the power density electric heating water tank 4: a heating water tank liquid level gauge 13, the bottom and the top of liquid level gauge 13 joining water box; A radiator thermometer 16, radiator thermometer 16 is arranged on water tank inside; A water tank outlet temperature meter 17 is arranged in the water tank outlet 44; A water tank return water temperature meter 18 is arranged in the water tank return pipe 45.
As shown in Figure 1, the suction inlet of ebullator 5 is communicated with high power density electric heating water tank 4 bottoms by water tank outlet 44, and the outlet of ebullator 5 is connected with steam generator secondary side hand hole temporary interface 2 by the second circulation heating hose 35.On ebullator 5 discharge pipes, be respectively arranged with the heat cycles flowmeter 19 and first high pressure isolation valve 38.In addition, between the outlet of ebullator 5 and suction inlet low discharge reflux pipeline 47 is set, low discharge reflux pipeline 47 is provided with ebullator reverse flow valve 27.
As shown in Figure 1, in first high pressure isolation valve, 38 upstreams at steam generator secondary side hand hole temporary interface 2 places drain pipe and corresponding hand hole temporary interface drain valve 37 are set.
As shown in Figure 1, the return pipe 45 of high power density electric heating water tank 4 is connected by the high-order temporary interface 3 of the first circulation heating hose 34 and steam generator secondary side and constitutes the heat cycles return piping, on this pipeline, be provided with the 3rd high pressure isolation valve 41, be equipped with high-order temporary interface bleeder pipe 48 and corresponding high-order temporary interface air release 40 in the provided upstream of the 3rd high pressure isolation valve 41 near the high-order temporary interface of steam generator secondary side 3 places.
As shown in Figure 1, preposition supercharge pump 6, big flow pressuring pump 7, low discharge pressuring pump 8, adjustable pressure reflux 10 and suppress outlet solenoid valve 12 and constituted the pressuring pump unit jointly, wherein big flow pressuring pump 7 and low discharge pressuring pump 8 are arranged in parallel, the exit of every pressuring pump is provided with big flow pressuring pump outlet non-return valve 29 and low discharge pressuring pump outlet non-return valve 30 respectively, and preposition supercharge pump 6 is arranged on the upstream of two pressuring pumps and suppresses intake head for it provides.The suction inlet pipeline of preposition supercharge pump 6 is communicated with and is provided with between the two with high power density electric heating water tank 4 outlets suppresses suction inlet isolation valve 28.After two pressuring pump 7,8 parallel connections, gather at its pump discharge an adjustable pressure reflux 10 is set on the pipeline, this reflux 10 can be opened reflux pipeline 51 when suppressing top hole pressure and be higher than certain value (this setting valve is adjustable), will suppress the suction inlet that fluid is back to preposition supercharge pump 6.Gather on the pipeline in the pressuring pump outlet, the downstream of adjustable pressure reflux 10 is provided with one and suppresses outlet solenoid valve 12, this solenoid valve 12 opens and closes to make and suppresses reflux pipeline 51 and is interrupted injection suppresses fluid under the operating mode that pressuring pump 7,8 is not stopped transport, and suppresses the realization of technology to guarantee crawl.The outlet of suppressing of pressuring pump unit is connected with steam generator secondary side hand hole temporary interface 2 by high-pressure hose 36, between high-pressure hose 36 and the steam generator secondary side hand hole temporary interface 2 one second high pressure isolation valve 39 is set.
As shown in Figure 1, suppress the outlet gather on the pipeline, at adjustable pressure reflux 10 and suppress outlet and be provided with between the solenoid valve 12 and suppress delivery gauge 20, be respectively arranged with one between outlet solenoid valve 12 and the high-pressure hose 36 and suppress and export on the spot tensimeter 21, a bypass release pipeline 49 and a safety valve release pipeline 50 suppressing.
As shown in Figure 1, suppress and export on the spot that the provided upstream of tensimeter 21 is equipped with a pressure gauge isolator valve 33 on the spot.
As shown in Figure 1, series connection is provided with a safety valve pipeline isolation valve 32 and one and suppresses outlet safety valve 11 on the safety valve release pipeline 50.
As shown in Figure 1, bypass release pipeline 49 has been provided with one and has suppressed by-pass flow isolation valve 31 and two bypass release variable valve 9.Two bypass release variable valve 9 are arranged in parallel and constitute the variable valve group, suppress by-pass flow isolation valve 31 and are arranged on variable valve group upstream.
As shown in Figure 1, two bypass release variable valve 9 and suppress the outlet safety valve 11 the downstream be aggregated into system's drainage interface 14 places by pipeline.
All integrated being arranged in of following equipment is provided with in the standard size frame type container of strengthening structure: high power density electric heating water tank 4, ebullator 5, preposition supercharge pump 6, big flow pressuring pump 7, low discharge pressuring pump 8, bypass release variable valve 9, adjustable pressure reflux 10, suppress outlet safety valve 11, suppress outlet solenoid valve 12, heating water tank liquid level gauge 13, system's drainage interface 14, system water supplement interface 15, radiator thermometer 16, water tank outlet temperature meter 17, water tank return water temperature meter 18, heat cycles flowmeter 19, suppress delivery gauge 20, suppress and export tensimeter 21 on the spot, water tank moisturizing isolation valve 22, tank drains isolation valve 23, water tank air release 24, funnel 25, the hydrophobic isolation valve 26 of funnel, ebullator reverse flow valve 27, suppress suction inlet isolation valve 28, big flow pressuring pump outlet non-return valve 29, low discharge pressuring pump outlet non-return valve 30, suppress by-pass flow isolation valve 31, safety valve pipeline isolation valve 32, pressure gauge isolator valve 33 on the spot, low discharge reflux pipeline 47, high-order temporary interface bleeder pipe 48, bypass release pipeline 49, safety valve release pipeline 50.
Principle of work below in conjunction with hydraulic testing integrated system before accompanying drawing 1 explanation a kind of PWR nuclear power plant steam generator secondary side labour provided by the present invention: after steam generator secondary side 1 and the common water-filling exhaust of this hydraulic testing integrated system are finished, keep first high pressure isolation valve 38 and the 3rd high pressure isolation valve 41 to open, close water tank moisturizing isolation valve 22, tank drains isolation valve 23, hand hole temporary interface drain valve 37 and high-order temporary interface air release 40, start ebullator 5, after confirming that by heat cycles flowmeter 19 the system water circulation is normally set up, open electric heaters in the heating water tank 4.Ebullator 5 will through the heating demineralized water in the interim access port 2 steam in jection generator secondary sides 1 of the secondary side hand hole of steam generator bottom, hot water after mixing, flows back to heating water tank 4 heating that circulates by the high-order interim access port 3 of steam generator in steam generator.In the circulation heating process, can be interrupted and open water tank air release 24 to discharge the gas that discharges in the demineralized water.When (primary side of steam generator) outside steam generator secondary side 1 housing and the tube sheet is heated in the temperature range of regulation, close the electric heater in the heating water tank 4, the ebullator 5 of closing down cuts out first high pressure isolation valve 38 and the 3rd high pressure isolation valve 41 isolation cycle heating circuits is arranged.
Behind the isolation cycle heating circuit, open heating water tank moisturizing isolation valve 22, start preposition supercharge pump 6, big flow pressuring pump 7 successively, the pressuring pump unit sucks demineralized water by high-pressure hose 36 steam in jection generator secondary sides 1 from heating water tank 4, suppresses according to the program of suppressing of system.If system rises to after the certain pressure, system boosted too fast when pressuring pump 7 full flows were suppressed, then reduce the flow of pressuring pump 7 by variable frequency adjustment, also changeable low discharge pressuring pump 8 is suppressed, along with the rising of system pressure, low discharge pressuring pump 8 also can be suppressed flow by the variable frequency adjustment reduction and be no more than the testing requirements value to guarantee that system boosts.When boost in pressure to each pressure platform of regulation and during the resulting pressure platform, according to the relevant rules of the steam generator hydraulic testing steam generator secondary side and related system member are checked.For guaranteeing that the demineralized water that injects during the bulge test does not influence the temperature of steam generator secondary side 1 and main body pressure-bearing material, suppress that can be interrupted the suitable electrical heating elements of input in the process is incubated heating to suppressing water in the water tank 4.
Boost in system, be provided with safety valve 11 on the pressure dwelling loop, steam generator secondary side 1 is carried out overpressure protection.The rate of pressure rise control of system is realized by pressuring pump frequency conversion, the big flow pressuring pump 7 of switching and low discharge pressuring pump 8 and adjusting high precision bypass release variable valve 9, in the time can't accurately controlling rate of pressure rise continuously, can adopt the control mode control of crawl outlet solenoid valve 12 to suppress.When system carries out step-down, control rate of pressure reduction by the flow of adjusting high precision bypass release variable valve 9, can keep pressuring pump suitably moving under the flow in case of necessity, be no more than the testing requirements limit value with the rate of pressure reduction of guaranteeing system.
In conjunction with the accompanying drawings embodiments of the invention have been done detailed description above, but the present invention is not limited to the foregoing description, in the ken that those of ordinary skills possessed, can also under the prerequisite that does not break away from aim of the present invention, makes various variations.The content that is not described in detail in the instructions of the present invention all can adopt prior art, and for example the high power density electric heating water tank 4, ebullator 5, preposition supercharge pump 6, big flow pressuring pump 7, low discharge pressuring pump 8, bypass release variable valve 9, adjustable pressure reflux 10, suppress outlet safety valve 11, suppress outlet solenoid valve 12, heating water tank liquid level gauge 13, system's drainage interface 14, system water supplement interface 15, radiator thermometer 16, water tank outlet temperature meter 17, water tank return water temperature meter 18, heat cycles flowmeter 19, suppress delivery gauge 20, suppress and export tensimeter 21 on the spot, water tank moisturizing isolation valve 22, tank drains isolation valve 23, water tank air release 24, funnel 25, the hydrophobic isolation valve 26 of funnel, ebullator reverse flow valve 27, suppress suction inlet isolation valve 28, big flow pressuring pump outlet non-return valve 29, low discharge pressuring pump outlet non-return valve 30, suppress by-pass flow isolation valve 31, safety valve pipeline isolation valve 32, pressure gauge isolator valve 33 grades all can adopt the product of any model in the prior art on the spot.
Claims (6)
1. hydraulic testing integrated system before a PWR nuclear power plant steam generator secondary side is used as a servant, it comprises the pressuring pump that can suppress in steam generator secondary side (1), it is characterized in that: it also comprises electric heating water tank (4) and ebullator (5), described pressuring pump is in parallel with ebullator (5), the suction inlet of the inlet of pressuring pump and ebullator (5) all is communicated with the water tank outlet (44) of electric heating water tank (4), the outlet of suppressing delivery side of pump and ebullator (5) all is communicated with the hand hole temporary interface (2) of steam generator secondary side (1), and the water tank return pipe (45) of electric heating water tank (4) is communicated with the high-order temporary interface (3) of steam generator secondary side (1).
2. hydraulic testing integrated system before a kind of PWR nuclear power plant steam generator secondary side labour according to claim 1 is characterized in that: be provided with preposition supercharge pump (6) between described electric heating water tank (4) and the pressuring pump.
3. hydraulic testing integrated system before a kind of PWR nuclear power plant steam generator secondary side labour according to claim 1 and 2, it is characterized in that: described pressuring pump comprises big flow pressuring pump (7) and low discharge pressuring pump (8), big flow pressuring pump (7) and low discharge pressuring pump (8) parallel connection.
4. hydraulic testing integrated system before a kind of PWR nuclear power plant steam generator secondary side labour according to claim 3 is characterized in that: be provided with adjustable pressure reflux (10) between the big flow pressuring pump (7) after the described parallel connection and the outlet of low discharge pressuring pump (8) and the hand hole temporary interface (2).
5. hydraulic testing integrated system before a kind of PWR nuclear power plant steam generator secondary side labour according to claim 4, it is characterized in that: be provided with bypass release pipeline (49) between described adjustable pressure reflux (10) and the hand hole temporary interface (2), be communicated with between bypass release pipeline (49) and the system's drainage interface (14), be provided with two bypass release variable valve in parallel between bypass release pipeline (49) and the system's drainage interface (14).
6. hydraulic testing integrated system before a kind of PWR nuclear power plant steam generator secondary side labour according to claim 5, it is characterized in that: also be provided with safety valve release pipeline (50) between described adjustable pressure reflux (10) and the hand hole temporary interface (2), be communicated with between safety valve release pipeline (50) and the system's drainage interface (14), be provided with spring safety valve (11) between safety valve release pipeline (50) and the system's drainage interface (14).
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| CN2010101304928A CN102194535B (en) | 2010-03-11 | 2010-03-11 | Pre-service hydrostatic test integrated system on secondary side of steam generator |
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| CN2010101304928A CN102194535B (en) | 2010-03-11 | 2010-03-11 | Pre-service hydrostatic test integrated system on secondary side of steam generator |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN102194534A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | High-precision pressing and depressing process for pre-service hydraulic pressure test of steam generator secondary side |
| CN103424233A (en) * | 2012-05-24 | 2013-12-04 | 中国核动力研究设计院 | Hydraulic test pressure control system |
| CN104575639A (en) * | 2015-01-27 | 2015-04-29 | 深圳东方锅炉控制有限公司 | Full-automatic hydrostatic test device for nuclear power container |
| CN107293340A (en) * | 2017-06-28 | 2017-10-24 | 西安交通大学 | A kind of small-sized steam generator thermal hydraulic analysis pilot system |
| CN109799142A (en) * | 2018-12-20 | 2019-05-24 | 中广核核电运营有限公司 | Nuclear power station water pressure test loop heating system and circular heating method |
| CN109974990A (en) * | 2019-04-08 | 2019-07-05 | 南京讯联智能科技有限公司 | A kind of working life test macro of wind-powered electricity generation heat dissipation plate under extreme conditions |
| CN110057865A (en) * | 2019-05-14 | 2019-07-26 | 哈尔滨工程大学 | Marine vapor generator secondary side boiling heat transfer analytical equipment |
| CN110264867A (en) * | 2019-04-22 | 2019-09-20 | 中国舰船研究设计中心 | A kind of steam generator secondary side dynamic characteristic test simulator |
| CN110579405A (en) * | 2019-08-29 | 2019-12-17 | 中广核核电运营有限公司 | Auxiliary water supply system of nuclear power station and heating method thereof |
| CN110853785A (en) * | 2019-11-20 | 2020-02-28 | 苏州热工研究院有限公司 | Method for analyzing output capacity fault of nuclear power pressurized water reactor unit |
| CN111351021A (en) * | 2018-12-21 | 2020-06-30 | 核动力运行研究所 | Method for preheating tube plate of steam generator secondary side hydrostatic test |
| CN111736639A (en) * | 2020-06-09 | 2020-10-02 | 重庆城市管理职业学院 | Temperature monitoring system applied to cold-chain logistics |
| CN113421670A (en) * | 2021-06-18 | 2021-09-21 | 中国核动力研究设计院 | Nuclear power plant accident regulation quantitative analysis method and system |
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Cited By (18)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102194534A (en) * | 2010-03-11 | 2011-09-21 | 中国核动力研究设计院 | High-precision pressing and depressing process for pre-service hydraulic pressure test of steam generator secondary side |
| CN102194534B (en) * | 2010-03-11 | 2013-05-01 | 中国核动力研究设计院 | High-precision pressing and depressing process for pre-service hydraulic pressure test of steam generator secondary side |
| CN103424233A (en) * | 2012-05-24 | 2013-12-04 | 中国核动力研究设计院 | Hydraulic test pressure control system |
| CN104575639A (en) * | 2015-01-27 | 2015-04-29 | 深圳东方锅炉控制有限公司 | Full-automatic hydrostatic test device for nuclear power container |
| CN107293340B (en) * | 2017-06-28 | 2019-08-23 | 西安交通大学 | A kind of small-sized steam generator thermal hydraulic analysis pilot system |
| CN107293340A (en) * | 2017-06-28 | 2017-10-24 | 西安交通大学 | A kind of small-sized steam generator thermal hydraulic analysis pilot system |
| CN109799142B (en) * | 2018-12-20 | 2021-11-09 | 中广核核电运营有限公司 | Circulating heating system and circulating heating method for nuclear power station hydrostatic test |
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| CN110264867B (en) * | 2019-04-22 | 2021-08-03 | 中国舰船研究设计中心 | Steam generator secondary side dynamic characteristic test simulation device |
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