CN102194535B - 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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- CN102194535B CN102194535B CN2010101304928A CN201010130492A CN102194535B CN 102194535 B CN102194535 B CN 102194535B CN 2010101304928 A CN2010101304928 A CN 2010101304928A CN 201010130492 A CN201010130492 A CN 201010130492A CN 102194535 B CN102194535 B CN 102194535B
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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 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 pre-service hydrostatic test integrated system on secondary side of steam generator that is applied to PWR nuclear power plant (station).
Background technology
Secondary pre-service hydraulic pressure test of steam generator is important node and the milestone in the PWR nuclear power plant nuclear island equipment erection schedule.Its scope has covered steam generator secondary side and relative system (comprising main feed system, auxiliary feedwater system, main steam system, drainage etc.) pipeline and isolation boundary-valve.This test comprises that steam generator shell heats up, the 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 secondary pre-service hydraulic pressure test of steam generator of nuclear power station 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 heat stepwise water fillings; Adopt common separate unit pressuring pump to boost.This temporary system mainly contains following shortcoming: system heats up and causes very slowly the test period very long; The equipment dispersed placement, large, the on-the-spot temporary interface of the spatial volume that takies 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 a kind of pre-service hydrostatic test integrated system on secondary side of steam generator, this system performance is reliable and stable, can realize even, the rapidly intensification 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: a kind of PWR nuclear power plant pre-service hydrostatic test integrated system on secondary side of steam generator, it comprises the pressuring pump that can suppress in the steam generator secondary side, electric heating water tank and ebullator, described pressuring pump is in parallel with ebullator, the entrance 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 circulation delivery side of pump and all be communicated with the hand hole temporary interface of steam generator secondary side, the water container backwater 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 large flow pressuring pump and low discharge pressuring pump, and large flow pressuring pump and low discharge pressuring pump are in parallel.
Large 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, are provided with reflux pipeline between adjustable pressure reflux and the preposition supercharging pump intake.
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 drainage interface.
Useful technique effect of the present invention is: system of the present invention adopts the mode of direct circulation heating to realize being rapidly heated of steam generator shell.This system adopts the modularization Integrated design, all constituents of this system all can be integrated in the template posture container.Have the characteristics such as volume is little, function is complete, degree of regulation is high, security is high.On the basis that the hydraulic testing rules that satisfy the 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 rapidly intensification 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, everywhere isolation boundary favorable sealing property.This systemic-function is comprehensive, can realize corresponding technological requirement in the different tests stage of secondary pre-service hydraulic pressure test of steam generator, has guaranteed that heating process before 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 Heating Cyclic loop.Steam generator secondary side can directly be filled with cold water (demineralized water), by this circulating-heating process system the demineralized water in the steam generator is carried out circulating-heating, thereby steam generator shell is heated up.Adopt 1 horizontal high performance centrifugal pump as ebullator, this ebullator frame bottom is provided with beam integrated Systems balanth requirement 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, arrange 1 cover setting valve adjustable suppress reflux, when system suppresses top hole pressure and is higher than setting valve, this is suppressed reflux and automatically opens reflux pipeline, 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 poor operating mode of transformation 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 at every, with the security of operation that guarantees equipment and operating personnel's safety.
Description of drawings
Fig. 1 is that the structure of a kind of pre-service hydrostatic test integrated system on secondary side of steam generator provided by the present invention forms synoptic diagram.
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. large flow pressuring pump; 8. low discharge pressuring pump; 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 drainage interface; 15. system water supplement interface; 16. radiator thermometer; 17. water tank outlet temperature meter; 18. water container backwater thermometer; 19. Heating Cyclic flowmeter; 20. suppress delivery gauge; Export on the spot tensimeter 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. large flow pressuring pump outlet non-return valve; 30. low discharge pressuring pump outlet non-return valve; 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 circulating-heating flexible pipe; 35. the second circulating-heating flexible pipe; 36. high-pressure hose; 37. hand hole temporary interface drain valve; 38. the first high pressure isolation valve; 39. the second high pressure isolation valve; 40. high-order temporary interface air release; 41. third high is pressed isolation valve; 42. water tank filling pipe; 43. tank drains pipe; 44. water tank outlet; 45 water container backwater pipes; 46. gas outlet; 47. low discharge reflux pipeline; 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, a kind of PWR nuclear power plant pre-service hydrostatic test integrated system on secondary side of steam generator, it comprises high power density electric heating water tank 4, ebullator 5, preposition supercharge pump 6, large 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 drainage interface 14, system water supplement interface 15, radiator thermometer 16, water tank outlet temperature meter 17, water container backwater thermometer 18, Heating Cyclic flowmeter 19, suppress delivery gauge 20, suppress and export on the spot tensimeter 21, 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, large 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 circulating-heating flexible pipe 34, the second circulating-heating flexible pipe 35, high-pressure hose 36, hand hole temporary interface drain valve 37, the first high pressure isolation valve 38 that is communicated with steam generator secondary side hand hole temporary interface 2, the 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, press isolation valve 41 with the third high that the high-order temporary interface 3 of steam generator secondary side is communicated with, 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 arrange respectively water tank filling pipe 42, tank drains pipe 43, water tank outlet 44 and water container backwater pipe 45.Be provided with water tank moisturizing isolation valve 22 on the water tank filling pipe 42, the end that suspends of water tank filling pipe 42 is communicated with system water supplement interface 15.Be provided with tank drains isolation valve 23 on the tank drains pipe 43.The top of high power density electric heating water tank 4 arranges gas outlet 46, be provided with water tank air release 24 on this gas outlet 46, the outlet of water tank gas outlet 46 arranges 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, 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 container backwater thermometer 18 is arranged in the water container backwater 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 circulating-heating flexible pipe 35.Be respectively arranged with Heating Cyclic flowmeter 19 and the first high pressure isolation valve 38 at ebullator 5 discharge pipes.In addition, between the outlet of ebullator 5 and suction inlet, low discharge reflux pipeline 47 is set, is provided with ebullator reverse flow valve 27 on the low discharge reflux pipeline 47.
As shown in Figure 1, in the 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 circulating-heating flexible pipe 34 and steam generator secondary side and consists of the Heating Cyclic return piping, on this pipeline, be provided with third high near the high-order temporary interface of steam generator secondary side 3 places and press isolation valve 41, press the provided upstream of isolation valve 41 to be equipped with high-order temporary interface bleeder pipe 48 and corresponding high-order temporary interface air release 40 in third high.
As shown in Figure 1, preposition supercharge pump 6, large flow pressuring pump 7, low discharge pressuring pump 8, adjustable pressure reflux 10 and suppress outlet solenoid valve 12 and jointly consisted of the pressuring pump unit, wherein large flow pressuring pump 7 and low discharge pressuring pump 8 are arranged in parallel, the exit of every pressuring pump arranges respectively large flow pressuring pump outlet non-return valve 29 and low discharge pressuring pump outlet non-return valve 30, 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 pumps 7,8 parallel connections, gather pipeline at its pump discharge an adjustable pressure reflux 10 is set, 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 fluid and be back to the suction inlet of preposition supercharge pump 6.Gather on the pipeline in the pressuring pump outlet, the downstream of adjustable pressure reflux 10 arranges 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 technique 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, and second high pressure isolation valve 39 is set between high-pressure hose 36 and the steam generator secondary side hand hole temporary interface 2.
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 an on the spot pressure gauge isolator valve 33.
As shown in Figure 1, series connection arranges 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 consist of 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 drainage interface 14 places by pipeline.
Following equipment all integrated being arranged in 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, large 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 drainage interface 14, system water supplement interface 15, radiator thermometer 16, water tank outlet temperature meter 17, water container backwater thermometer 18, Heating Cyclic flowmeter 19, suppress delivery gauge 20, suppress and export on the spot tensimeter 21, 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, large 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 accompanying drawing 1 explanation a kind of PWR nuclear power plant pre-service hydrostatic test integrated system on secondary side of steam generator 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 the first high pressure isolation valve 38 and third high to press 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 Heating Cyclic flowmeter 19 the system water circulation is normally set up, open heating water tank 4 interior electric heaters.Ebullator 5 will through the heating demineralized water in the interim access port 2 steam injection 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 by the high-order interim access port 3 of steam generator and carries out circulating-heating in steam generator.In the circulating-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 the first high pressure isolation valve 38 and has third high to press isolation valve 41 isolation cycle heating circuits.
Behind the isolation cycle heating circuit, open heating water tank moisturizing isolation valve 22, start successively preposition supercharge pump 6, large flow pressuring pump 7, the pressuring pump unit sucks demineralized water by high-pressure hose 36 steam injection 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 affect 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 carries out Heat preservation to suppressing water in the water tank 4.
Boost in system, pressure dwelling loop is provided with safety valve 11, and 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 large 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, come controlled hypotension speed by the flow of adjusting high precision bypass release variable valve 9, can keep in case of necessity pressuring pump suitably moving under the flow, be no more than the testing requirements limit value with the rate of pressure reduction of guaranteeing system.
The above has done detailed description to embodiments of the invention by reference to the accompanying drawings, but the present invention is not limited to above-described embodiment, in the ken that those of ordinary skills possess, can also make various variations under the prerequisite that does not break away from aim of the present invention.The content that is not described in detail in the instructions of the present invention all can adopt prior art, and for example high power density electric heating water tank 4, ebullator 5, preposition supercharge pump 6, large 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 drainage interface 14, system water supplement interface 15, radiator thermometer 16, water tank outlet temperature meter 17, water container backwater thermometer 18, Heating Cyclic flowmeter 19, suppress delivery gauge 20, suppress and export on the spot tensimeter 21, 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, large 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. PWR nuclear power plant pre-service hydrostatic test integrated system on secondary side of steam generator, it comprises the pressuring pump that can suppress in the 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 entrance 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 container backwater pipe (45) of electric heating water tank (4) is communicated with the high-order temporary interface (3) of steam generator secondary side (1).
2. a kind of PWR nuclear power plant pre-service hydrostatic test integrated system on secondary side of steam generator 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. a kind of PWR nuclear power plant pre-service hydrostatic test integrated system on secondary side of steam generator according to claim 1 and 2, it is characterized in that: described pressuring pump comprises large flow pressuring pump (7) and low discharge pressuring pump (8), large flow pressuring pump (7) and low discharge pressuring pump (8) parallel connection.
4. a kind of PWR nuclear power plant pre-service hydrostatic test integrated system on secondary side of steam generator according to claim 3, it is characterized in that: be provided with adjustable pressure reflux (10) between the large 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), be provided with reflux pipeline (51) between the suction inlet of adjustable pressure reflux (10) and preposition supercharge pump (6).
5. a kind of PWR nuclear power plant pre-service hydrostatic test integrated system on secondary side of steam generator 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 drainage interface (14), be provided with two bypass release variable valve in parallel between bypass release pipeline (49) and the System drainage interface (14).
6. a kind of PWR nuclear power plant pre-service hydrostatic test integrated system on secondary side of steam generator 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 drainage interface (14), be provided with spring safety valve (11) between safety valve release pipeline (50) and the System 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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| CN102194535A CN102194535A (en) | 2011-09-21 |
| CN102194535B true CN102194535B (en) | 2013-03-20 |
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Families Citing this family (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN104575639B (en) * | 2015-01-27 | 2016-11-09 | 深圳东方锅炉控制有限公司 | A kind of full-automatic water compression testing device of 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| CN110057865B (en) * | 2019-05-14 | 2022-09-27 | 哈尔滨工程大学 | Secondary side boiling heat transfer analysis device of marine steam generator |
| CN110579405B (en) * | 2019-08-29 | 2022-05-06 | 中广核核电运营有限公司 | Auxiliary water supply system of nuclear power station and heating method thereof |
| CN110853785B (en) * | 2019-11-20 | 2021-08-17 | 苏州热工研究院有限公司 | Method for analyzing output capacity fault of nuclear power pressurized water reactor unit |
| CN111736639B (en) * | 2020-06-09 | 2021-09-21 | 重庆城市管理职业学院 | Temperature monitoring system applied to cold-chain logistics |
| CN113421670B (en) * | 2021-06-18 | 2022-05-13 | 中国核动力研究设计院 | Nuclear power plant accident regulation quantitative analysis method and system |
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| FR2765720B1 (en) * | 1997-07-01 | 1999-10-01 | Framatome Sa | METHOD FOR CLEANING THE SECONDARY PART OF A STEAM GENERATOR OF A NUCLEAR REACTOR COOLED BY PRESSURIZED WATER |
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