CN105945014A - Steam blowing system and method for main steam pipeline of nuclear power plant - Google Patents
Steam blowing system and method for main steam pipeline of nuclear power plant Download PDFInfo
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- CN105945014A CN105945014A CN201610494465.6A CN201610494465A CN105945014A CN 105945014 A CN105945014 A CN 105945014A CN 201610494465 A CN201610494465 A CN 201610494465A CN 105945014 A CN105945014 A CN 105945014A
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- steam
- vaporizer
- pressure
- secondary circuit
- blowpipe
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B08—CLEANING
- B08B—CLEANING IN GENERAL; PREVENTION OF FOULING IN GENERAL
- B08B9/00—Cleaning hollow articles by methods or apparatus specially adapted thereto
- B08B9/02—Cleaning pipes or tubes or systems of pipes or tubes
- B08B9/027—Cleaning the internal surfaces; Removal of blockages
- B08B9/032—Cleaning the internal surfaces; Removal of blockages by the mechanical action of a moving fluid, e.g. by flushing
- B08B9/0321—Cleaning the internal surfaces; Removal of blockages by the mechanical action of a moving fluid, e.g. by flushing using pressurised, pulsating or purging fluid
- B08B9/0328—Cleaning the internal surfaces; Removal of blockages by the mechanical action of a moving fluid, e.g. by flushing using pressurised, pulsating or purging fluid by purging the pipe with a gas or a mixture of gas and liquid
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- Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- Control Of Turbines (AREA)
- Engine Equipment That Uses Special Cycles (AREA)
Abstract
The invention discloses a steam blowing system and method for a main steam pipeline of a nuclear power plant. The system comprises a water feed pump outlet isolation door (1), a high-pressure heater bypass pipe (2) and an external steam inflation valve set (8). An outlet of the water feed pump outlet isolation door (1) is connected to an inlet of the high-pressure heater bypass pipe (2). The external steam inflation valve set (8) is installed in an open hole in a water supply pipeline behind the water feed pump outlet isolation door (1). By means of the method, the time needed for heating external steam to steam reaching pipe blowing parameters through heat generated by rotation of a main pump (main nucleolus draught fan) is shorter, the pipe blowing time is greatly shortened, and a test run working period is shortened.
Description
Technical field:
The present invention relates to technical field of nuclear power, be specifically related to a kind of nuclear power station main steam line steam blowing is
System and method.
Background technology:
The blowing method that PWR nuclear power plant main steam line is used at present has:
(1) frictional heat that when utilizing heat examination, the rotation of nuclear island main pump produces adds hot water so that it is become steam, utilizes
These steam-line blowings.Thermal Finite produced by main pump, water vapor latent heat is very big, therefore produces steam
Time is the longest, vapour amount little, and the blowpipe used time is the longest, and can only symbolically purge, and does not reaches blowpipe and wants
Ask；
(2) compressed air blowpipe is utilized.GB50235 requirement, jet chimney jet chimney blows
Pipe, utilizes compressed air blowpipe, does not meets the requirement of GB50235, does not has replacing of temperature during blowpipe
Change blowpipe effect is bad；
HTGR steam parameter is more much higher than presurized water reactor, and the cleannes of its pipeline require tightened up, mesh
Before also there is no suitable method.
Summary of the invention:
Present invention aims to current Secondary Circuit of PWR main steam line purging institute user
The problem that the deficiency of method, HTGR secondary circuit main steam line do not have appropriate method, it is provided that Yi Zhonghe
The system and method for nuclear power station main steam line steam blowing, it had both been suitable for pressurized-water reactor nuclear power plant, also had been adapted for
In HTGR Nuclear Power Plant.
For reaching above-mentioned purpose, the present invention adopts the following technical scheme that and realizes:
The system of a kind of nuclear power station main steam line steam blowing, adds including feed pump outlet isolating door, high pressure
Hot device shunt valve and external steam are filled with valve group, wherein,
The outlet of feed pump outlet isolating door is connected to the entrance of high-pressure heater shunt valve, exports at feed pump
On feedwater piping after isolating door, perforate is installed external steam and is filled with valve group.
The present invention is further improved by, and external steam is filled with valve group and includes connecting successively against filling vapour direction
Non-return flap, regulation door and the cut-off gate connect.
The present invention is further improved by, and also includes vaporizer and pressure vessel；Wherein,
The outlet of pressure vessel is connected to the first entrance of vaporizer, and the first outlet of vaporizer is connected to pressure
The entrance of container, the outlet of high-pressure heater shunt valve is connected to the second entrance of vaporizer；Vaporizer is pipe
Shell heat exchanger, shell-side is the primary side of vaporizer, and tube side is the secondary side of vaporizer, the first of vaporizer
Entrance accesses the primary side of vaporizer, the primary side outlet that the first outlet is vaporizer of vaporizer, vaporizer
The second entrance access the secondary side entrance of vaporizer, the secondary side outlet of vaporizer is connected to the of vaporizer
Two outlets；The system being connected with vaporizer primary side becomes primary Ioops, with vaporizer secondary side is connected is
System becomes secondary circuit.
The present invention is further improved by, and the working medium in pressure vessel is by the power drive in pressure vessel
Device drives, and wherein, for pressurized-water reactor nuclear power plant, its working medium is demineralized water, and driving means is main pump,
For HTGR Nuclear Power Plant, its working medium is helium, and driving means is Helium fan.
The present invention is further improved by, and also includes that main inlet throttle-stop valve, blowpipe control door and deafener temporarily；Its
In,
The entrance of main inlet throttle-stop valve is connected to the second outlet of vaporizer；The outlet of main inlet throttle-stop valve uses steam turbine plant to provide
False door core block, and main inlet throttle-stop valve door rod is taken down, and is connected to interim blowpipe by interim pipe and controls door
Entrance, the outlet of interim blowpipe control door connects the entrance of deafener.
The present invention is further improved by, high-pressure heater shunt valve, the secondary side of vaporizer, main inlet throttle-stop valve
Before all have hydrophobic valve, these hydrophobic valves are referred to as secondary circuit hydrophobic valve.
A kind of method of nuclear power station main steam line steam blowing, comprises the following steps:
1) feed pump is exported isolating door to close tight, secondary circuit hydrophobic valve is opened, interim blowpipe is controlled door
Crack 5%；
2) external steam is filled with valve group by external steam and is filled with high-pressure heater shunt valve, vaporizer
Secondary side is until main inlet throttle-stop valve, interim blowpipe control in front of the door, and a small amount of steam is controlled door by interim blowpipe, disappeared
Sound device enters air；
3) in being filled with steam course, being filled with of gate control steam is regulated by what external steam was filled with in valve group
, there is not water slug, and ensure that the temperature rise speed of vaporizer is less than its temperature in speed, it is ensured that steam is filled with gently
Rise limit value；
4) when from interim blowpipe control the steam that goes out of door row without water after, close interim blowpipe control door, two times
Road hydrophobic valve, secondary circuit pressure, temperature will slowly rise subsequently, in intensification, boost process, it is ensured that
The intensification of vaporizer, the rate of rise are less than its temperature, pressure limit；
5) start the Power Drive Unit in pressure vessel, rotated by driving means and primary Ioops working medium is followed
Circulation moves up, and primary Ioops working medium absorbs the heat of secondary circuit steam, and temperature slowly raises, and, drives meanwhile
Device frictional heat, heats the working medium of primary Ioops further；
6) along with secondary circuit pressure, the lifting of temperature, after secondary circuit steam pressure is equal to external steam pressure,
External steam will be unable to be re-filled with secondary circuit；
7) primary Ioops working medium is under vaporizer Power Drive Unit spin friction produces the heating of heat, temperature, pressure
Power raises further, transfers heat to secondary circuit simultaneously, heats the steam of secondary circuit further so that two
Loop steam pressure, temperature raise further, after secondary circuit steam pressure is higher than external steam pressure, outward
The non-return flap that portion's steam is filled with in valve group will turn off；
8) after vapor (steam) temperature and pressure meet blowpipe requirement in secondary circuit, open blowpipe and control a blowpipe temporarily；
9) during blowpipe, secondary circuit pressure reduces, when secondary circuit pressure is less than external steam pressure,
The non-return flap that external steam is filled with in valve group would automatically turn on, and external steam is filled with in secondary circuit, when two times
After road vapor (steam) temperature is close with external steam temperature, closes interim blowpipe and control door；
10) repeat above 6) to 9) process, until system purge is clean.
The present invention is further improved by, and external steam is starting trouble steam, heating boiler steam or neighbour
Machine auxiliary steam.
Compared with prior art, present invention have the advantage that:
The system and method for a kind of nuclear power station main steam line steam blowing that the present invention provides, this has following several
Aspect clear advantage:
1, utilize main pump (main core blower fan) to rotate the heat produced and external steam is heated to the steaming of steam blow parameters
The time that vapour needs is shorter, is greatly shortened the washing pipe time, reduces the test run duration；
2, blowpipe vapor (steam) temperature is higher, and blowpipe effect is more preferable；
3, solving HTGR main steam line cannot the problem of blowpipe.
4, this system mainly make use of the original equipment of nuclear power station, and the extra equipment increased is less, cost of investment
Few.
The currently used method of the method has compared following several respects clear advantage:
1, utilize main pump (main core blower fan) to rotate the heat produced and external steam is heated to the steaming of steam blow parameters
The time that vapour needs is shorter, is greatly shortened the washing pipe time, reduces the test run duration；
2, blowpipe vapor (steam) temperature is higher, and blowpipe effect is more preferable；
3, solving HTGR main steam line cannot the problem of blowpipe.
Accompanying drawing illustrates:
Fig. 1 is the structured flowchart of the system of the present invention a kind of nuclear power station main steam line steam blowing.
Detailed description of the invention:
Below in conjunction with accompanying drawing, the present invention is made further instructions.
As it is shown in figure 1, the system of a kind of nuclear power station main steam line steam blowing of present invention offer, including
Feed pump exports isolating door 1, high-pressure heater shunt valve 2, vaporizer 3, main inlet throttle-stop valve 4, deafener 5, blows
Interim door 6, pressure vessel 7 and the external steam of controlling of pipe is filled with valve group 8, wherein, feed pump outlet isolation
The outlet of door 1 is connected to the entrance of high-pressure heater shunt valve 2, giving after feed pump outlet isolating door 1
On waterpipe, perforate is installed external steam and is filled with valve group 8；The outlet of pressure vessel 7 is connected to vaporizer 3
First entrance, the first outlet of vaporizer 3 is connected to the entrance of pressure vessel 7, high-pressure heater shunt valve 2
Outlet be connected to the second entrance of vaporizer 3；Vaporizer 3 is shell-and-tube heat exchanger, and shell-side is vaporizer 3
Primary side, tube side is the secondary side of vaporizer 3, vaporizer 3 first entrance access vaporizer 3 one
Secondary side, the primary side outlet that the first outlet is vaporizer 3 of vaporizer 3, the second entrance of vaporizer 3 connects
Entering the secondary side entrance of vaporizer 3, the secondary side outlet of vaporizer 3 is connected to the second outlet of vaporizer 3；
The entrance of main inlet throttle-stop valve 4 is connected to the second outlet of vaporizer 3；The outlet of main inlet throttle-stop valve 4 uses steam turbine plant to carry
The false door core of confession is blocked, and main inlet throttle-stop valve door rod takes down, and is connected to interim blowpipe control door 6 by interim pipe
Entrance, interim blowpipe controls the outlet of door 6 and connects the entrance of deafener 5.
Described external steam is filled with non-return flap, regulation door and the cut-off gate that valve group 8 includes being sequentially connected with.
Working medium in pressure vessel 7 is driven by the Power Drive Unit in pressure vessel 7, wherein, for setting-out
For reactor of nuclear power plant, its working medium is demineralized water, and driving means is main pump, comes for HTGR Nuclear Power Plant
Saying, its working medium is helium, and driving means is Helium fan.
The method of a kind of nuclear power station main steam line steam blowing that the present invention provides, specifically includes following step
Rapid:
1) connect temporary pipeline from steam turbine main inlet throttle-stop valve door rod, connect interim blowpipe and control door, pass through temporary pipeline
Access deafener；
2) feed pump outlet valve is closed tight, is followed by interim tee T at feed pump outlet valve, and installs interim
Fill steam valve door；
3) utilize external steam (starting trouble, heating boiler, adjacent machine auxiliary steam etc.) to high water-adding system,
Steam generator secondary circuit, main steam system fill steam；
4) one loop of nuclear power station main pump (main core blower fan) is utilized to rotate the heat produced by vaporizer to two times
Road steam heating, in making system, vapor (steam) temperature raises further, and pressure increases further；
5) after vapor (steam) temperature and pressure meet blowpipe requirement in secondary circuit, open blowpipe and control door temporarily and blow
Pipe；
6) above procedure is repeated, until system purge is clean.
Below as a example by the system of certain nuclear power generating sets main steam line purging, the specific embodiment party of this invention is described
Formula.
The available outside vapour source of this unit include 1 can produce 42t/h parameter be 1.25MPa, 193 DEG C
The electric boiler of steam and can produce 10t/h parameter be 1.25MPa, the coal-burning boiler of 193 DEG C of steam 5.
Total steam production is 92t/h.The power of this unit main pump (main core blower fan) is 4500KW.
1) connect temporary pipeline from steam turbine main inlet throttle-stop valve door rod, connect interim blowpipe and control door, pass through temporary pipeline
Access deafener；
2) feed pump outlet valve is closed tight, be followed by interim tee T at feed pump outlet valve, and installation is faced
Time fill steam valve door group, temporary valve group include non-return valve, regulation valve, stop valve；
3) external steam (starting trouble, heating boiler, adjacent machine auxiliary steam etc.) is utilized to add shunt valve to height
Road, steam generator secondary circuit, main steam system fill steam；
4) pipeline used blowpipe during filling vapour carries out heating coil, and heating coil cuts out all hydrophobic after completing
Exhaust valve, starts boosting.After pressure reaches 1.0MPa in secondary coolant circuit system, open the examination of interim washing pipe door
Blowing, record steam drain pressure during examination is blown, steam drain pressure adds declared working condition main steam line resistance
It is formal blowpipe pressure.This factory's exhaust port pressure is 0.5MPa, it is thus determined that formal blowpipe pressure is
More than 2.7MPa.
5) after examination has been blown, closing interim blowpipe door, system continues boosting.When system pressure reaches
After 1.25MPa, non-return flap is closed, and fills vapour and stops；
6) starting main pump (main core blower fan), the heat utilizing main pump (main core blower fan) spin friction to produce leads to
Pervaporation device heats to secondary circuit steam, and in making system, vapor (steam) temperature raises further, and pressure increases further
Greatly；
7) after evaporator outlet steam pressure reaches 3.5MPa, open blowpipe and control a blowpipe temporarily, when
After system pressure is less than outside pressure of steam supply, non-return flap is opened, and system fills vapour again.When evaporator outlet temperature
After degree reaches about 200 DEG C, closing interim washing pipe door, system is boosted, when system pressure is more than 1.25MPa
After, non-return flap is closed.System under the heat that main pump (main core blower fan) spin friction produces, pressure
Temperature raises further, until pressure arrives 3.5MPa.
8) above procedure is repeated, until system purge is clean.
Claims (8)
1. the system of a nuclear power station main steam line steam blowing, it is characterised in that include that feed pump exports
Isolating door (1), high-pressure heater shunt valve (2) and external steam are filled with valve group (8), wherein,
The outlet of feed pump outlet isolating door (1) is connected to the entrance of high-pressure heater shunt valve (2),
On feedwater piping after feed pump outlet isolating door (1), perforate is installed external steam and is filled with valve group (8).
The system of a kind of nuclear power station main steam line steam blowing the most according to claim 1, its feature
Being, external steam is filled with valve group (8) and includes against filling non-return flap, the regulation door that vapour direction is sequentially connected with
And cut-off gate.
The system of a kind of nuclear power station main steam line steam blowing the most according to claim 1, its feature
It is, also includes vaporizer (3) and pressure vessel (7)；Wherein,
The outlet of pressure vessel (7) is connected to the first entrance of vaporizer (3), the first of vaporizer (3)
Outlet is connected to the entrance of pressure vessel (7), and the outlet of high-pressure heater shunt valve (2) is connected to evaporation
Second entrance of device (3)；Vaporizer (3) is shell-and-tube heat exchanger, shell-side be vaporizer (3) once
Side, tube side is the secondary side of vaporizer (3), and the first entrance of vaporizer (3) accesses vaporizer (3)
Primary side, the primary side outlet that the first outlet is vaporizer (3) of vaporizer (3), vaporizer (3)
Second entrance accesses the secondary side entrance of vaporizer (3), and the secondary side outlet of vaporizer (3) is connected to steam
Send out the second outlet of device (3)；The system being connected with vaporizer (3) primary side becomes primary Ioops, with steaming
The system sending out the connection of device (3) secondary side becomes secondary circuit.
The system of a kind of nuclear power station main steam line steam blowing the most according to claim 3, its feature
Being, the working medium in pressure vessel (7) is driven by the Power Drive Unit in pressure vessel (7), its
In, for pressurized-water reactor nuclear power plant, its working medium is demineralized water, and driving means is main pump, for High Temperature Gas
For cold dome nuclear power station, its working medium is helium, and driving means is Helium fan.
The system of a kind of nuclear power station main steam line steam blowing the most according to claim 3, its feature
It is, also includes that main inlet throttle-stop valve (4), blowpipe control door (6) and deafener (5) temporarily；Wherein,
The entrance of main inlet throttle-stop valve (4) is connected to the second outlet of vaporizer (3)；The outlet of main inlet throttle-stop valve (4) is adopted
The false door core provided with steam turbine plant is blocked, and main inlet throttle-stop valve door rod is taken down, and is connected to face by interim pipe
Time blowpipe control the entrance of door (6), interim blowpipe controls the outlet of door (6) and connects the entrance of deafener (5).
The system of a kind of nuclear power station main steam line steam blowing the most according to claim 3, its feature
Be, high-pressure heater shunt valve (2), the secondary side of vaporizer (3), main inlet throttle-stop valve (4) be front all have thin
Penstock, these hydrophobic valves are referred to as secondary circuit hydrophobic valve.
7. the method for a nuclear power station main steam line steam blowing, it is characterised in that comprise the following steps:
1) feed pump exports isolating door (1) to close tight, secondary circuit hydrophobic valve is opened, by interim blowpipe
Control door (6) crack 5%；
2) by external steam by external steam be filled with valve group (8) be filled with high-pressure heater shunt valve (2),
The secondary side of vaporizer (3) until main inlet throttle-stop valve (4), interim blowpipe to control door (6) front, a small amount of steam
Control door (6) by interim blowpipe, deafener (5) enters air；
3) the regulation gate control steam being filled with in valve group (8) by external steam in being filled with steam course
Be filled with speed, it is ensured that steam is filled with gently, and water slug do not occurs, and ensures the temperature rise speed of vaporizer (3)
Degree is less than its temperature limit；
4) after the steam discharged from interim blowpipe control door (6) is without water, close interim blowpipe and control door
(6), secondary circuit hydrophobic valve, secondary circuit pressure, temperature will slowly rise subsequently, heat up, rise press through
Cheng Zhong, it is ensured that the intensification of vaporizer (3), the rate of rise are less than its temperature, pressure limit；
5) start the Power Drive Unit in pressure vessel (7), rotated by driving means and make primary Ioops
Working medium circulation flows, and primary Ioops working medium absorbs the heat of secondary circuit steam, and temperature slowly raises, meanwhile,
Driving means frictional heat, heats the working medium of primary Ioops further；
6) along with secondary circuit pressure, the lifting of temperature, after secondary circuit steam pressure is equal to external steam pressure,
External steam will be unable to be re-filled with secondary circuit；
7) primary Ioops working medium is under vaporizer (3) Power Drive Unit spin friction produces the heating of heat, temperature
Degree, pressure raise further, transfer heat to secondary circuit simultaneously, heat the steam of secondary circuit further,
Secondary circuit steam pressure, temperature are raised further, when secondary circuit steam pressure is higher than external steam pressure
After, the non-return flap that external steam is filled with in valve group (8) will turn off；
8) after vapor (steam) temperature and pressure meet blowpipe requirement in secondary circuit, open blowpipe and control a blowpipe temporarily；
9) during blowpipe, secondary circuit pressure reduces, when secondary circuit pressure is less than external steam pressure,
The non-return flap that external steam is filled with in valve group (8) would automatically turn on, and external steam is filled with in secondary circuit, when
After secondary circuit vapor (steam) temperature is close with external steam temperature, closes interim blowpipe and control door (6)；
10) repeat above 6) to 9) process, until system purge is clean.
The method of a kind of nuclear power station main steam line steam blowing the most according to claim 7, its feature
Being, external steam is starting trouble steam, heating boiler steam or adjacent machine auxiliary steam.
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| CN201610494465.6A CN105945014B (en) | 2016-06-28 | 2016-06-28 | A kind of system and method for nuclear power station main steam line steam blowing |
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Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106981322A (en) * | 2017-04-26 | 2017-07-25 | 西安热工研究院有限公司 | A kind of system and method for being used to verify HTGR start and stop heaping equipment function |
| CN107150055A (en) * | 2017-07-04 | 2017-09-12 | 山东中实易通集团有限公司 | The auxiliary vapour purging system and method not restricted before a kind of unit starting by steam |
| CN108278586A (en) * | 2018-03-14 | 2018-07-13 | 西安热工研究院有限公司 | A kind of system and method for HTGR Nuclear Power Plant primary Ioops heating and dehumidification |
| CN108435719A (en) * | 2018-02-06 | 2018-08-24 | 华电电力科学研究院有限公司 | A kind of extremely cold area long range steam pipe line blowing method |
| CN111677966A (en) * | 2020-05-28 | 2020-09-18 | 清华大学 | Pipeline communication device for high-temperature gas cooled reactor |
| CN113123836A (en) * | 2019-12-30 | 2021-07-16 | 上海电气电站设备有限公司 | Back pressure steam turbine starting method |
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Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN201954251U (en) * | 2010-10-14 | 2011-08-31 | 中广核工程有限公司 | Nuclear power station compressed air vessel system |
| CN104190676A (en) * | 2014-08-06 | 2014-12-10 | 苏州热工研究院有限公司 | Corrosion-product removing and coating applying device for inner wall of pipe of nuclear power plant |
| CN104966536A (en) * | 2015-07-14 | 2015-10-07 | 西安交通大学 | High-temperature working medium heat exchange test system using heat conducting oil as hot fluid and test method |
| CN105605551A (en) * | 2016-03-14 | 2016-05-25 | 西安热工研究院有限公司 | System and method for heating boiler feed water through steam turbine bypass steam |
| CN105642620A (en) * | 2014-11-13 | 2016-06-08 | 广东核电合营有限公司 | Method and device for cleaning and coating of interior of nuclear power station pipeline through aerodynamic force |
| CN205949420U (en) * | 2016-06-28 | 2017-02-15 | 西安热工研究院有限公司 | System for nuclear power station main steam pipeline steam blowing |
-
2016
- 2016-06-28 CN CN201610494465.6A patent/CN105945014B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN201954251U (en) * | 2010-10-14 | 2011-08-31 | 中广核工程有限公司 | Nuclear power station compressed air vessel system |
| CN104190676A (en) * | 2014-08-06 | 2014-12-10 | 苏州热工研究院有限公司 | Corrosion-product removing and coating applying device for inner wall of pipe of nuclear power plant |
| CN105642620A (en) * | 2014-11-13 | 2016-06-08 | 广东核电合营有限公司 | Method and device for cleaning and coating of interior of nuclear power station pipeline through aerodynamic force |
| CN104966536A (en) * | 2015-07-14 | 2015-10-07 | 西安交通大学 | High-temperature working medium heat exchange test system using heat conducting oil as hot fluid and test method |
| CN105605551A (en) * | 2016-03-14 | 2016-05-25 | 西安热工研究院有限公司 | System and method for heating boiler feed water through steam turbine bypass steam |
| CN205949420U (en) * | 2016-06-28 | 2017-02-15 | 西安热工研究院有限公司 | System for nuclear power station main steam pipeline steam blowing |
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106981322A (en) * | 2017-04-26 | 2017-07-25 | 西安热工研究院有限公司 | A kind of system and method for being used to verify HTGR start and stop heaping equipment function |
| CN106981322B (en) * | 2017-04-26 | 2018-10-23 | 西安热工研究院有限公司 | A kind of system and method for verifying high temperature gas cooled reactor start and stop heaping equipment function |
| CN107150055A (en) * | 2017-07-04 | 2017-09-12 | 山东中实易通集团有限公司 | The auxiliary vapour purging system and method not restricted before a kind of unit starting by steam |
| CN108435719A (en) * | 2018-02-06 | 2018-08-24 | 华电电力科学研究院有限公司 | A kind of extremely cold area long range steam pipe line blowing method |
| CN108435719B (en) * | 2018-02-06 | 2020-05-12 | 华电电力科学研究院有限公司 | Method for purging long-distance steam pipeline in extremely cold region |
| CN108278586A (en) * | 2018-03-14 | 2018-07-13 | 西安热工研究院有限公司 | A kind of system and method for HTGR Nuclear Power Plant primary Ioops heating and dehumidification |
| CN113123836A (en) * | 2019-12-30 | 2021-07-16 | 上海电气电站设备有限公司 | Back pressure steam turbine starting method |
| CN113123836B (en) * | 2019-12-30 | 2022-07-19 | 上海电气电站设备有限公司 | Back pressure steam turbine starting method |
| CN111677966A (en) * | 2020-05-28 | 2020-09-18 | 清华大学 | Pipeline communication device for high-temperature gas cooled reactor |
| CN113819453A (en) * | 2021-10-28 | 2021-12-21 | 华能山东石岛湾核电有限公司 | Device and method for increasing feed water temperature in starting stage of high-temperature gas cooled reactor |
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