CN205949420U - System for nuclear power station main steam pipeline steam blowing - Google Patents
System for nuclear power station main steam pipeline steam blowing Download PDFInfo
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- CN205949420U CN205949420U CN201620666408.7U CN201620666408U CN205949420U CN 205949420 U CN205949420 U CN 205949420U CN 201620666408 U CN201620666408 U CN 201620666408U CN 205949420 U CN205949420 U CN 205949420U
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Abstract
The utility model discloses a system for nuclear power station main steam pipeline steam blowing, fill valve group (8) including water -feeding pump export isolation gating (1), high pressure feed water heater by pass pipe (2) and outside steam, wherein, water -feeding pump export isolation gating's (1) exit linkage is at the entry of high pressure feed water heater by pass pipe (2), and the trompil is installed outside steam and is filled and organize (8) into the valve on the water feeding pipe behind water -feeding pump export isolation gating (1). The utility model discloses utilize the rotatory heat that produces of main pump (main examine fan) shorter to the time that the steam of blowpipe parameter needs with outside steam heating, shorten the washing pipe time greatly, the reduction test run time limit for a project.
Description
Technical field：
The utility model be related to technical field of nuclear power and in particular to a kind of nuclear power station main steam line steam blowing be
System.
Background technology：
The blowing method that PWR nuclear power plant main steam line is adopted at present has：
(1) rotate the frictional heat heating water producing so as to become steam using nuclear island main pump during heat examination, using these steam
Blowpipe.Due to thermal Finite produced by main pump, water vapor latent heat is very big, therefore produce that steaming time is very long, vapour amount seldom, blow
Very long when effective, and can only symbolically purge, do not reach blowpipe requirement；
(2) utilize compressed air blowpipe.GB50235 requires, and jet chimney carries out blowpipe with jet chimney, using compression
Air blowpipe, does not meet the requirement of GB50235, does not have the alternately change blowpipe effect of temperature bad during blowpipe；
Much higher than presurized water reactor of HTGR steam parameter, the cleannes of its pipeline require tightened up, also do not have at present
There is suitable method.
Utility model content：
The purpose of this utility model is to purge institute user for current Secondary Circuit of PWR main steam line
The deficiency of method, HTGR secondary circuit main steam line do not have the problem of appropriate method, there is provided the main steaming of a seed nucleus nuclear power station
The system of steam pipe road steam blowing, it was both suitable for pressurized-water reactor nuclear power plant, was also suitable for HTGR Nuclear Power Plant.
For reaching above-mentioned purpose, the utility model adopts the following technical scheme that to be realized：
A kind of system of nuclear power station main steam line steam blowing, by feedwater pump discharge isolating door, high-pressure heater
Road pipe and external steam are filled with valve group, wherein,
The outlet of feedwater pump discharge isolating door is connected to the entrance of high-pressure heater shunt valve, in feedwater pump discharge isolating door
On feedwater piping afterwards, perforate is installed external steam and is filled with valve group.
The utility model is further improved by, and external steam is filled with valve group and includes being sequentially connected against filling vapour direction
Non-return flap, adjust door and cut-off gate.
The utility model is further improved by, and also includes evaporimeter and pressure vessel；Wherein,
The outlet of pressure vessel is connected to the first entrance of evaporimeter, and the first outlet of evaporimeter is connected to pressure vessel
Entrance, the outlet of high-pressure heater shunt valve is connected to the second entrance of evaporimeter；Evaporimeter is shell-and-tube heat exchanger, and shell-side is
The primary side of evaporimeter, tube side is the secondary side of evaporimeter, and the first entrance of evaporimeter accesses the primary side of evaporimeter, evaporimeter
First outlet be evaporimeter a side outlet, the second entrance of evaporimeter accesses the secondary side entrance of evaporimeter, evaporimeter
Secondary side outlet be connected to the second outlet of evaporimeter；The system being connected with evaporimeter primary side becomes primary Ioops, with steaming
The system sending out the connection of device secondary side becomes secondary circuit.
The utility model is further improved by, and the working medium in pressure vessel passes through the power drive dress in pressure vessel
Put driving, wherein, for pressurized-water reactor nuclear power plant, its working medium is demineralized water, and driving means are main pump, for HTGR
For nuclear power station, its working medium is helium, and driving means are Helium fan.
The utility model is further improved by, and also includes main inlet throttle-stop valve, blowpipe and controls door and muffler temporarily；Wherein,
The entrance of main inlet throttle-stop valve is connected to the second outlet of evaporimeter；The outlet of main inlet throttle-stop valve adopts the false door that steam turbine plant provides
Core is blocked, and main inlet throttle-stop valve door rod is taken down, and is connected to, by interim pipe, the entrance that interim blowpipe controls door, and interim blowpipe controls
The outlet of door connects the entrance of muffler.
The utility model is further improved by, before high-pressure heater shunt valve, the secondary side of evaporimeter, main inlet throttle-stop valve all
There is hydrophobic valve, these hydrophobic valves are referred to as secondary circuit hydrophobic valve.
Compared with prior art, the utility model has such advantages as：
A kind of system of nuclear power station main steam line steam blowing that the utility model provides, this has following several respects obvious
Advantage：
1st, utilize the heat that main pump (main core blower fan) rotation produces that external steam is heated to the steam needs of steam blow parameters
Time shorter, greatly shorten the washing pipe time, reduce the test run duration；
2nd, blowpipe vapor (steam) temperature is higher, and blowpipe effect is more preferable；
3rd, solve the problems, such as that HTGR main steam line cannot blowpipe.
4th, this system mainly make use of the original equipment of nuclear power station, and extra increased equipment is less, and cost of investment is few.
Brief description：
Fig. 1 is a kind of structured flowchart of the system of the utility model nuclear power station main steam line steam blowing.
Specific embodiment：
Below in conjunction with accompanying drawing, the utility model is made further instructions.
As shown in figure 1, a kind of system of nuclear power station main steam line steam blowing of the utility model offer, including feedwater
Pump discharge isolating door 1, high-pressure heater shunt valve 2, evaporimeter 3, main inlet throttle-stop valve 4, muffler 5, blowpipe control door 6, pressure temporarily
Container 7 and external steam are filled with valve group 8, and wherein, the outlet of feedwater pump discharge isolating door 1 is connected to high-pressure heater shunt valve
2 entrance, perforate on the feedwater piping after feedwater pump discharge isolating door 1 is installed external steam and is filled with valve group 8；Pressure vessel
7 outlet is connected to the first entrance of evaporimeter 3, and the first outlet of evaporimeter 3 is connected to the entrance of pressure vessel 7, and high pressure adds
The outlet of hot device shunt valve 2 is connected to the second entrance of evaporimeter 3；Evaporimeter 3 is shell-and-tube heat exchanger, and shell-side is evaporimeter 3
Primary side, tube side is the secondary side of evaporimeter 3, and the first entrance of evaporimeter 3 accesses the primary side of evaporimeter 3, evaporimeter 3
First outlet is a side outlet of evaporimeter 3, and the second entrance of evaporimeter 3 accesses the secondary side entrance of evaporimeter 3, evaporimeter
3 secondary side outlet is connected to the second outlet of evaporimeter 3；The entrance of main inlet throttle-stop valve 4 is connected to the second outlet of evaporimeter 3；Main
The outlet of porthole 4 is blocked using the false door core that steam turbine plant provides, and main inlet throttle-stop valve door rod takes down, and is connected to by interim pipe and faces
When blowpipe control the entrance of door 6, interim blowpipe controls the outlet of door 6 to connect the entrance of muffler 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.Pressure vessel
The Power Drive Unit that working medium in 7 is passed through in pressure vessel 7 drives, and wherein, for pressurized-water reactor nuclear power plant, its working medium is
Demineralized water, driving means are main pump, and for HTGR Nuclear Power Plant, its working medium is helium, helium wind based on driving means
Machine.
A kind of method of the system of the nuclear power station main steam line steam blowing being provided using the utility model, is specifically included
Following steps：
1) connect temporary pipeline from steam turbine main inlet throttle-stop valve door rod, connect interim blowpipe and control door, accessed by temporary pipeline and disappear
Sound device；
2) feed pump outlet valve is closed tight, is followed by interim three-way pipe in feed pump outlet valve, and installs and fill steam valve temporarily
Door；
3) utilize external steam (starting trouble, heating boiler, adjacent machine auxiliary steam etc.) to high water-adding system, steam generation
Device secondary circuit, main steam system fill steam；
4) heat that one loop of nuclear power station main pump (main core blower fan) rotation produces is utilized to pass through evaporimeter to secondary circuit steam
Heating, makes vapor (steam) temperature in system raise further, pressure increases further；
5) after vapor (steam) temperature and pressure meet blowpipe requirement in secondary circuit, open blowpipe and control a blowpipe temporarily；
6) repeat above procedure, until system purge is clean.
Below taking the system of certain nuclear power generating sets main steam line purging as a example, the specific embodiment party of this utility model is described
Formula.
The available outside vapour source of this unit include 1 can produce 42t/h parameter be 1.25MPa, 193 DEG C of steam
Electric boiler is 1.25MPa, the coal-burning boiler 5 of 193 DEG C of steam with producing 10t/h parameter.Total steam production is 92t/h.Should
The power of 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, accessed by temporary pipeline and disappear
Sound device；
2) feed pump outlet valve is closed tight, be followed by interim three-way pipe in feed pump outlet valve, and install and fill vapour temporarily
Valve group, temporary valve group includes non-return valve, regulating valve, stop valve；
3) external steam (starting trouble, heating boiler, adjacent machine auxiliary steam etc.) is utilized to send out to high plus bypass duct, steam
Raw device secondary circuit, main steam system fill steam；
4) pipeline during filling vapour, blowpipe used carries out heating coil, closes all hydrophobic exhaust steam valves after the completion of heating coil
Door, starts to boost.After pressure reaches 1.0MPa in secondary coolant circuit system, open interim washing pipe door examination and blow, remember during examination is blown
Record steam drain pressure, steam drain pressure adds that declared working condition main steam line resistance is formal blowpipe pressure.This factory's exhaust outlet
Pressure is 0.5MPa, it is thus determined that formal blowpipe pressure is more than 2.7MPa.
5) after the completion of examination is blown, close interim blowpipe door, system continues boosting.After system pressure reaches 1.25MPa, check
Door is closed, and fills vapour and stops；
6) start main pump (main core blower fan), given by evaporimeter using the heat that main pump (main core blower fan) spin friction produces
Secondary circuit steam heats, and so that vapor (steam) temperature in system is raised further, pressure increases further；
7) after evaporator outlet steam pressure reaches 3.5MPa, open blowpipe and control a blowpipe temporarily, work as system pressure
After outside pressure of steam supply, non-return flap is opened, and system fills vapour again.After evaporator outlet temperature reaches 200 DEG C about, close
Close interim washing pipe door, system is boosted, after system pressure is more than 1.25MPa, non-return flap is closed.System is at main pump (main core blower fan)
Under the heat that spin friction produces, pressure and temp raises further, until pressure reaches 3.5MPa.
8) repeat above procedure, until system purge is clean.
Claims (3)
1. a kind of system of nuclear power station main steam line steam blowing it is characterised in that include feedwater pump discharge isolating door (1),
High-pressure heater shunt valve (2) and external steam are filled with valve group (8), wherein,
The outlet of feedwater pump discharge isolating door (1) is connected to the entrance of high-pressure heater shunt valve (2), in feedwater pump discharge isolation
On feedwater piping after door (1), perforate is installed external steam and is filled with valve group (8).
2. a kind of system of nuclear power station main steam line steam blowing according to claim 1 is it is characterised in that outside steam
Vapour is filled with valve group (8) and includes against filling the non-return flap that vapour direction is sequentially connected, adjust door and cut-off gate.
3. a kind of system of nuclear power station main steam line steam blowing according to claim 1 is it is characterised in that also include
Evaporimeter (3) and pressure vessel (7)；Wherein,
The outlet of pressure vessel (7) is connected to the first entrance of evaporimeter (3), and the first outlet of evaporimeter (3) is connected to pressure
The entrance of container (7), the outlet of high-pressure heater shunt valve (2) is connected to the second entrance of evaporimeter (3)；Evaporimeter (3) is
Shell-and-tube heat exchanger, shell-side is the primary side of evaporimeter (3), and tube side is the secondary side of evaporimeter (3), the first of evaporimeter (3)
Entrance accesses the primary side of evaporimeter (3), and the first outlet of evaporimeter (3) is a side outlet of evaporimeter (3), evaporimeter
(3) second entrance accesses the secondary side entrance of evaporimeter (3), and the secondary side outlet of evaporimeter (3) is connected to evaporimeter (3)
Second outlet；The system being connected with evaporimeter (3) primary side becomes primary Ioops, the system being connected with evaporimeter (3) secondary side
Become secondary circuit；
The Power Drive Unit that working medium in pressure vessel (7) is passed through in pressure vessel (7) drives, wherein, for presurized water reactor core
For power station, its working medium is demineralized water, and driving means are main pump, and for HTGR Nuclear Power Plant, its working medium is helium,
Driving means are Helium fan；
Also include main inlet throttle-stop valve (4), blowpipe controls door (6) temporarily and muffler (5)；Wherein,
The entrance of main inlet throttle-stop valve (4) is connected to the second outlet of evaporimeter (3)；The outlet of main inlet throttle-stop valve (4) adopts steam turbine plant to provide
False door core block, and main inlet throttle-stop valve door rod is taken down, and the entrance that interim blowpipe controls door (6) is connected to by interim pipe, face
When blowpipe control the outlet of door (6) to connect the entrance of muffler (5)；
High-pressure heater shunt valve (2), the secondary side of evaporimeter (3), main inlet throttle-stop valve all have hydrophobic valve before (4), these drain valves
Door is referred to as secondary circuit hydrophobic valve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201620666408.7U CN205949420U (en) | 2016-06-28 | 2016-06-28 | System for nuclear power station main steam pipeline steam blowing |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201620666408.7U CN205949420U (en) | 2016-06-28 | 2016-06-28 | System for nuclear power station main steam pipeline steam blowing |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN205949420U true CN205949420U (en) | 2017-02-15 |
Family
ID=57968922
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201620666408.7U Active CN205949420U (en) | 2016-06-28 | 2016-06-28 | System for nuclear power station main steam pipeline steam blowing |
Country Status (1)
| Country | Link |
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| CN (1) | CN205949420U (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105945014A (en) * | 2016-06-28 | 2016-09-21 | 西安热工研究院有限公司 | Steam blowing system and method for main steam pipeline of nuclear power plant |
| CN112305391A (en) * | 2020-12-10 | 2021-02-02 | 三门核电有限公司 | Electromagnetic valve performance testing method for AP1000 main steam and main water supply isolation valve |
-
2016
- 2016-06-28 CN CN201620666408.7U patent/CN205949420U/en active Active
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105945014A (en) * | 2016-06-28 | 2016-09-21 | 西安热工研究院有限公司 | Steam blowing system and method for main steam pipeline of nuclear power plant |
| CN105945014B (en) * | 2016-06-28 | 2018-02-16 | 西安热工研究院有限公司 | A kind of system and method for nuclear power station main steam line steam blowing |
| CN112305391A (en) * | 2020-12-10 | 2021-02-02 | 三门核电有限公司 | Electromagnetic valve performance testing method for AP1000 main steam and main water supply isolation valve |
| CN112305391B (en) * | 2020-12-10 | 2023-09-08 | 三门核电有限公司 | Electromagnetic valve performance test method for AP1000 main steam and main water supply isolation valve |
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Legal Events
| Date | Code | Title | Description |
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| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant |