CN106352155A - Online pressure seal overhauling method of primary loop check valve of nuclear power plant - Google Patents
Online pressure seal overhauling method of primary loop check valve of nuclear power plant Download PDFInfo
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- CN106352155A CN106352155A CN201610848380.3A CN201610848380A CN106352155A CN 106352155 A CN106352155 A CN 106352155A CN 201610848380 A CN201610848380 A CN 201610848380A CN 106352155 A CN106352155 A CN 106352155A
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- Prior art keywords
- valve
- return valve
- flap
- nuclear power
- loop
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
- F16K—VALVES; TAPS; COCKS; ACTUATING-FLOATS; DEVICES FOR VENTING OR AERATING
- F16K43/00—Auxiliary closure means in valves, which in case of repair, e.g. rewashering, of the valve, can take over the function of the normal closure means; Devices for temporary replacement of parts of valves for the same purpose
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01M—TESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
- G01M3/00—Investigating fluid-tightness of structures
- G01M3/02—Investigating fluid-tightness of structures by using fluid or vacuum
- G01M3/26—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors
- G01M3/28—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for pipes, cables or tubes; for pipe joints or seals; for valves ; for welds
- G01M3/2876—Investigating fluid-tightness of structures by using fluid or vacuum by measuring rate of loss or gain of fluid, e.g. by pressure-responsive devices, by flow detectors for pipes, cables or tubes; for pipe joints or seals; for valves ; for welds for valves
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- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- Physics & Mathematics (AREA)
- General Physics & Mathematics (AREA)
- Details Of Valves (AREA)
Abstract
The invention relates to the technical field of a nuclear power plant, in particular to an online pressure seal overhauling method of a primary loop check valve of the nuclear power plant. According to the method, isolated overhauling of the valve is innovatively completed under the condition that cooling water in a primary loop system is prevented from being lower than lower low water level, the cooling water in the primary loop system is always higher than the lower low water level in an overhauling process, so that water filling and gas exhausting steps for dynamic gas exhausting or vacuum pumping at a startup stage of a unit are avoided, overhauling of the primary loop valve is really realized without the lower low water level, the manpower and material cost for overhauling is saved, the overhauling duration is greatly shortened, and the overhauling cost is reduced.
Description
Technical field
The present invention relates to nuclear power station technical field is and in particular to a kind of one loop of nuclear power station non-return valve on-line pressure sealant maintenance side
Method.
Background technology
In nuclear power station technical field of power generation, the cardinal principle of nuclear energy power generation is a large amount of heat energy being discharged using nuclear fission
Water is heated, is then generated electricity using the Steam Actuation steam turbine generator being formed, heat energy is changed into the process of electric energy.
Nuclear fission carries out and produces energy in reactor assembly, and by above-mentioned energy, water is heated and utilized the steaming producing
Vapour promotes the process that steam turbine generator is generated electricity to carry out all outside reactor assembly, accordingly, it would be desirable to by the way of certain
The conduction of the energy security that nuclear fission in reactor assembly is produced is out.
Existing nuclear power station will produce energy generally by the way of primary Ioops system adopts energy exchange in reactor assembly
Amount conduction is to outside, specific: the reactor core of reactor assembly utilizes fuel fission to produce huge heat energy, pumps into heap by main pump
The energy of the cooling water absorption heap in-core of core exports from heap in-core after being heated, and the coolant flow after energy absorption is through steam generation
Heat transfer u-shaped pipe in device, transfers thermal energy to the secondary circuit cooling water outside u-shaped pipe, again by main pump after release heat by tube wall
Send reactor core back to and re-start energy exchange, be again introduced into steam generator after output and carry out energy exchange, cooling water is so continuous
Ground, in airtight loop interior circulation, constantly by the energy conduction of reactor core nuclear fission generation out, is referred to as primary Ioops system.
During nuclear power station runs, the cooling water in primary Ioops system should be in the middle of operation all the time and meet one
Fixed water level requires, and the primary Ioops cooling water water level meeting the minimum requirements of nuclear power station trouble-free operation is referred to as low low water level.If
By the cooling water draining in primary Ioops system to less than low low water level, then unit is necessary for into action aerofluxuss in startup stage or takes out
Vacuum, so, will result in the prolongation of overhaul duration and the increase of the cost of overhaul.
It is connected with various separation valve doors in primary Ioops system, including the low low water level valve of similar d2rcp320vp,
Normal isolation maintenance to such valve can be carried out in low low water level, but because this valve is tested in unit descending phase pt
Unqualified probability is very big, according to related specifications, once pt test unqualified it is necessary to be keeped in repair this valve to ensure valve
Sealing, the cooling water at this valve then must be emptied by the maintenance stage, consequently, it is possible to can result in cold in primary Ioops system
But water is less than low low water level, causes the prolongation of overhaul duration and the increase of the cost of overhaul, and because nuclear power station maintenance duration is tight, such as
Where avoid the cooling water in primary Ioops system in the case of being less than low low water level, to complete the isolation maintenance to valve, become pendulum and exist
A difficult problem in face of testing staff.
Content of the invention
The present invention is directed to problems of the prior art, provides a kind of cooling water in avoiding primary Ioops system to be less than
The method completing the isolation maintenance to valve in the case of low low water level, has saved maintenance human and material resources cost, is conducive to shortening
Maintenance duration.
The present invention is achieved through the following technical solutions this purpose:
One loop of nuclear power station non-return valve on-line pressure sealant repair method, comprises the steps:
A, to around the non-return valve of Awaiting Overhaul arrange isolation protecting device, prevent primary Ioops cooling water leakage in maintenance process
To environment；
B, control primary Ioops systematic water level, primary Ioops systematic water level are dropped to below the valve gap position of non-return valve 50mm left
Right；
C, slowly unclamp valve gap and confirm that water level meets maintenance and requires, described isolation protecting device is collected and overflow from non-return valve opening
The primary Ioops cooling water going out；
D, dismounting flap bolt pull down the flap of non-return valve are overhauled, using the company to non-return valve downstream for the sealing-plug
Connect primary Ioops supervisor's passage to be blocked, and confirm that closure sealing is qualified；
Primary Ioops cooling water in e, emptying non-return valve upstream and valve pocket；
F, installation valve seat grinder tool are ground to valve seat, return dress flap, do valve tightness test and switch test
Verified；
After the completion of g, valve upkeep operation, clearing valve intracavity portion foreign body, it is filled with primary Ioops cooling water into valve pocket to being higher than
The water level of low low water level；
H, dismounting sealing-plug taking-up from valve pocket from non-return valve downstream passage；
I, installation sealing gasket and valve gap, and remove isolation protecting device.
Wherein, described isolation protecting device encloses the periphery being located at non-return valve, and is located at the lower section of non-return valve opening, described every
Drain pipe for discharging cooling water is also associated with preventer, this drain pipe and cooling water contain reservoir.
Wherein, the water level at the valve gap of non-return valve is higher than the low low water level of primary Ioops system.
Further, described step d carries out before disassembling section to flap, also includes verifying that flap whether there is bite now
As, and having gapless between detection flap and valve body both sides, the size in gap controls in 0.5～2mm, the maintenance bag to flap
Include flap decontamination and flap grinds.
Wherein, in described step d, after non-return valve downstream passage being blocked using sealing-plug, set up seal pressure, will
Non-return valve cools down water segregation with primary Ioops.
Wherein, volumetric expansion after described sealing-plug inflation, sets up seal pressure by the sealing-plug expanding, under non-return valve
Trip passage is blocked.
Wherein, described step f particularly as follows: first, carries out valve pocket decontamination, checks that flap and valve seat have zero defect；Then, grind
Valve grinding lobe and valve seat；Finally, carry out blue oil test after flap being arranged on valve seat.
Further, upkeep operation is carried out to valve and also include seal tightness test, non-return valve is installed and suppresses instrument pair
The sealing of valve is verified, dismantles flap again and take out after seal tightness test is qualified.
As preferred scheme, check that flap and valve seat have zero defect by dyeing inspection mode.
Wherein, described sealing-plug includes cock body, and the periphery of cock body offers arc groove, cock body offers recessed with circular arc
The medium channel of groove connection, is embedded with sealing joint strip, is connected with medium at the opening of described medium channel in described arc groove
Pipeline, also includes the positioning component for being positioned to cock body, and described positioning component is connected with cock body by a screw rod.
With respect to prior art, the invention has the benefit that
The one loop of nuclear power station non-return valve on-line pressure sealant repair method of the present invention, novelty in avoiding primary Ioops system
Cooling water be less than low low water level in the case of complete to the isolation of valve maintenance, due in primary Ioops system in maintenance process
Cooling water is consistently higher than low low water level, then avoid unit startup stage enter to take action aerofluxuss or evacuation water-filling aerofluxuss step
Suddenly, it is truly realized the no low low water level overhaul to primary Ioops valve, saved maintenance human and material resources cost, be conducive to significantly
Shorten maintenance duration, reduce the cost of overhaul.
Brief description
Fig. 1 is the schematic diagram arranging isolation protecting device around non-return valve.
Fig. 2 unclamps valve gap and carries out the hydrophobic schematic diagram of pressure release.
Fig. 3 is to take valve gap apart and pull down the schematic diagram that flap is overhauled.
Fig. 4 is schematic diagram non-return valve downstream passage being blocked using sealing-plug.
Fig. 5 is the cooling water of exhaust-valve intracavity, the schematic diagram to valve upkeep operation and clearing valve intracavity portion foreign body.
Fig. 6 is the schematic diagram being filled with cooling water into valve pocket.
Fig. 7 is to remove sealing-plug, the schematic diagram of installation flap.
Fig. 8 is to install valve gap, remove the schematic diagram after isolation protecting device.
Fig. 9 is the mounting structure schematic diagram of this sealing-plug.
Figure 10 is seal tightness test mounting structure schematic diagram.
In figure: 1- valve body, 2- valve gap, 3- isolation protecting device, 4- drain pipe, 5- flap, 6- sealing-plug, 61- cock body,
62- arc groove, 63- sealing joint strip, 64- medium pipeline, 7- cooling water, 8- positioning component, 9- screw rod, 10- tests valve gap,
11- control station, 12- pressuring pump.
Specific embodiment
Describe the present invention below in conjunction with drawings and the specific embodiments.
Embodiment 1.
As shown in figures 1-8, a kind of one loop of nuclear power station non-return valve on-line pressure sealant repair method of the present embodiment, is starting to examine
Carry out the preparation of some row, the non-return valve upstream line of isolation Awaiting Overhaul before repairing, do not empty medium, downstream primary Ioops water
Position controls in prescribed limit, and scene prepares construction and prepares corresponding instrument, specifically includes following steps:
A, to around the non-return valve of Awaiting Overhaul arrange isolation protecting device 3, prevent cooling water 7 in maintenance process from leaking to ring
In border；Described isolation protecting device 3 encloses the periphery being located at non-return valve, and is fixed on the lower section of non-return valve opening, for collect from
The cooling water 7 overflowing at non-return valve opening, described isolation protecting device 3 is also associated with the drain pipe for discharging cooling water 7
4, this drain pipe 4 contains reservoir with cooling water 7；
B, control primary Ioops systematic water level, by primary Ioops systematic water level drop to non-return valve valve gap 2 position (non-return valve
Water level at valve gap 2 is higher than the low low water level of primary Ioops system), it is to avoid after unclamping valve gap 2, cooling water 7 sprays；
C, unclamp valve gap 2 and carry out that pressure release is hydrophobic, described isolation protecting device 3 collects the cooling water overflowing from non-return valve opening
7, and cooling water 7 is delivered to by cooling water 7 by drain pipe 4 contains container；
Also include verifying that flap 5 whether there is bite phenomenon, and have gapless between detection flap 5 and valve body 1 both sides,
The size in gap controls in 0.5～2mm；
D, dismounting flap 5 bolt pull down the flap 5 of non-return valve are overhauled, and the maintenance to flap 5 includes flap 5
Dirty and flap 5 grinds；
Using sealing-plug 6 and positioning component 8, non-return valve downstream passage is blocked, set up seal pressure, to non-return valve
Downstream passage is blocked, and non-return valve is isolated with primary Ioops cooling water 7；
Cooling water 7 in e, emptying non-return valve valve pocket it is ensured that the internal anhydrous state of valve pocket, and to the decontamination of valve pocket inside at
Reason；
F, installation test valve gap 10, carry out upkeep operation to valve, first, carry out valve pocket decontamination, by dyeing inspection side
Formula checks that flap 5 and valve seat have zero defect；Then, flap 5 and valve seat are ground；Finally, carry out after flap 5 being arranged on valve seat
Blue oil test；
As shown in Figure 10, upkeep operation is carried out to valve and also includes seal tightness test, non-return valve is installed and suppresses instrument,
Joint test control station 11 and pressuring pump 12 are verified to the sealing of valve, again by flap 5 after seal tightness test is qualified
Dismantle and take out；
After the completion of g, upkeep operation, clearing valve intracavity portion foreign body, check valve gap 2 sealing surface, be filled with into valve pocket and configure
Boron water, flood to flap 5 installation bolt；
Within the limits prescribed, pressure release simultaneously removes sealing-plug 6, and installs fixing flap 5 for h, confirmation primary Ioops water level；
I, installation valve gap 2, and remove isolation protecting device 3, site clearing.
Embodiment 2.
As shown in figure 9, the present embodiment provides a kind of sealing-plug 6, including cock body 61, it is recessed that the periphery of cock body 61 offers circular arc
Groove 62, cock body 61 is offered the medium channel being connected with arc groove 62, is embedded with sealing joint strip in described arc groove 62
63, it is connected with medium pipeline 64 at the opening of described medium channel, also include the positioning component for being positioned to cock body 61
8, described positioning component 8 is connected with cock body 61 by a screw rod 9.
Embodiment described above only have expressed the several embodiments of the present invention, and its description is more concrete and detailed, but simultaneously
Therefore the restriction to the scope of the claims of the present invention can not be interpreted as.It should be pointed out that for those of ordinary skill in the art
For, without departing from the inventive concept of the premise, some deformation can also be made and improve, these broadly fall into the guarantor of the present invention
Shield scope.Therefore, the protection domain of patent of the present invention should be defined by claims.
Claims (10)
1. one loop of nuclear power station non-return valve on-line pressure sealant repair method is it is characterised in that comprise the steps:
A, isolation protecting device is set to around the non-return valve of Awaiting Overhaul, prevents in maintenance process primary Ioops cooling water leakage to ring
In border；
B, control primary Ioops systematic water level, primary Ioops systematic water level is dropped to below the valve gap position of non-return valve 50mm；
C, slowly unclamp valve gap and confirm that water level meets maintenance and requires, described isolation protecting device is collected and overflowed from non-return valve opening
Primary Ioops cooling water；
D, dismounting flap bolt pull down the flap of non-return valve are overhauled, using the connection one to non-return valve downstream for the sealing-plug
Loop supervisor's passage is blocked, and confirms that closure sealing is qualified；
Primary Ioops cooling water in e, emptying non-return valve upstream and valve pocket；
F, installation valve seat grinder tool are ground to valve seat, return dress flap, do valve tightness test and carry out with switch test
Checking；
After the completion of g, valve upkeep operation, clearing valve intracavity portion foreign body, it is filled with primary Ioops cooling water into valve pocket to higher than low
The water level of water level；
H, dismounting sealing-plug taking-up from valve pocket from non-return valve downstream passage；
I, installation sealing gasket and valve gap, and remove isolation protecting device.
2. one loop of nuclear power station non-return valve on-line pressure sealant repair method according to claim 1 it is characterised in that described every
Enclose the periphery being located at non-return valve, and the lower section positioned at non-return valve opening from preventer, described isolation protecting device is also connected with
There is the drain pipe for discharging cooling water, this drain pipe and cooling water contain reservoir.
3. one loop of nuclear power station non-return valve on-line pressure sealant repair method according to claim 1 is it is characterised in that described step
In rapid b, the water level at the valve gap of non-return valve is higher than the low low water level of primary Ioops system.
4. one loop of nuclear power station non-return valve on-line pressure sealant repair method according to claim 1 is it is characterised in that described step
Rapid d carries out before disassembling section to flap, also includes verifying that flap whether there is bite phenomenon, and detection flap and valve body both sides
Between have gapless, the size in gap controls in 0.5～2mm, the maintenance of flap is included with flap decontamination and flap grinds.
5. one loop of nuclear power station non-return valve on-line pressure sealant repair method according to claim 1 is it is characterised in that described step
In rapid d, after non-return valve downstream passage being blocked using sealing-plug, set up seal pressure, non-return valve is cooled down with primary Ioops
Water segregation.
6. one loop of nuclear power station non-return valve on-line pressure sealant repair method according to claim 5 is it is characterised in that described close
Volumetric expansion after blocking inflation, sets up seal pressure by the sealing-plug expanding, non-return valve downstream passage is blocked.
7. one loop of nuclear power station non-return valve on-line pressure sealant repair method according to claim 1 is it is characterised in that described step
Rapid f particularly as follows: first, carries out valve pocket decontamination, checks that flap and valve seat have zero defect；Then, flap and valve seat are ground；Finally,
Carry out blue oil test after flap is arranged on valve seat.
8. one loop of nuclear power station non-return valve on-line pressure sealant repair method according to claim 7 is it is characterised in that to valve
Carry out upkeep operation and also include seal tightness test, installation on non-return valve is suppressed instrument and the sealing of valve is verified, close
Again flap is dismantled after envelope property pass the test and take out.
9. one loop of nuclear power station non-return valve on-line pressure sealant repair method according to claim 7 is it is characterised in that pass through
Color test mode checks that flap and valve seat have zero defect.
10. one loop of nuclear power station non-return valve on-line pressure sealant repair method according to claim 1 is it is characterised in that described
Sealing-plug includes cock body, and the periphery of cock body offers arc groove, cock body is offered the medium channel being connected with arc groove,
It is embedded with sealing joint strip in described arc groove, at the opening of described medium channel, is connected with medium pipeline, also include for right
The positioning component that cock body is positioned, described positioning component is connected with cock body by a screw rod.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610848380.3A CN106352155B (en) | 2016-09-23 | 2016-09-23 | One loop of nuclear power station non-return valve on-line pressure sealant repair method |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610848380.3A CN106352155B (en) | 2016-09-23 | 2016-09-23 | One loop of nuclear power station non-return valve on-line pressure sealant repair method |
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| CN106352155B CN106352155B (en) | 2018-06-19 |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107179169A (en) * | 2017-06-14 | 2017-09-19 | 中广核工程有限公司 | A kind of nuclear power station check valve action test set and test method |
| CN111570360A (en) * | 2020-04-24 | 2020-08-25 | 岭东核电有限公司 | Nuclear power station unit safety injection pipeline check valve sealing abnormity processing method |
| CN112037947A (en) * | 2020-08-11 | 2020-12-04 | 中广核核电运营有限公司 | Method for processing abnormal water injection of third-sealing main pump |
| CN113464689A (en) * | 2021-04-19 | 2021-10-01 | 中核核电运行管理有限公司 | Online sealing performance measurement sealing plug of large-diameter nuclear-grade check valve |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3681920A (en) * | 1969-01-20 | 1972-08-08 | Atomenergi Ab | Method and means for generating electricity and vaporizing a liquid in a thermal power station |
| US20110100006A1 (en) * | 2009-11-03 | 2011-05-05 | Korea Advanced Institute Of Science And Technology | Integrated process for water-hydrogen-electricity nuclear gas-cooled reactor |
| CN203520891U (en) * | 2013-08-21 | 2014-04-02 | 中国广核集团有限公司 | Steam generator secondary side cooling system of nuclear power station and connection component thereof |
| CN103915124A (en) * | 2013-10-18 | 2014-07-09 | 中广核核电运营有限公司 | Nuclear power station conventional island desalted water distribution system full-stop overhauling method |
| CN105805368A (en) * | 2014-12-28 | 2016-07-27 | 黑龙江宏宇电站设备有限公司 | A no-load running check valve for a power station and a no-load running method thereof |
-
2016
- 2016-09-23 CN CN201610848380.3A patent/CN106352155B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3681920A (en) * | 1969-01-20 | 1972-08-08 | Atomenergi Ab | Method and means for generating electricity and vaporizing a liquid in a thermal power station |
| US20110100006A1 (en) * | 2009-11-03 | 2011-05-05 | Korea Advanced Institute Of Science And Technology | Integrated process for water-hydrogen-electricity nuclear gas-cooled reactor |
| CN203520891U (en) * | 2013-08-21 | 2014-04-02 | 中国广核集团有限公司 | Steam generator secondary side cooling system of nuclear power station and connection component thereof |
| CN103915124A (en) * | 2013-10-18 | 2014-07-09 | 中广核核电运营有限公司 | Nuclear power station conventional island desalted water distribution system full-stop overhauling method |
| CN105805368A (en) * | 2014-12-28 | 2016-07-27 | 黑龙江宏宇电站设备有限公司 | A no-load running check valve for a power station and a no-load running method thereof |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107179169A (en) * | 2017-06-14 | 2017-09-19 | 中广核工程有限公司 | A kind of nuclear power station check valve action test set and test method |
| CN111570360A (en) * | 2020-04-24 | 2020-08-25 | 岭东核电有限公司 | Nuclear power station unit safety injection pipeline check valve sealing abnormity processing method |
| CN112037947A (en) * | 2020-08-11 | 2020-12-04 | 中广核核电运营有限公司 | Method for processing abnormal water injection of third-sealing main pump |
| CN113464689A (en) * | 2021-04-19 | 2021-10-01 | 中核核电运行管理有限公司 | Online sealing performance measurement sealing plug of large-diameter nuclear-grade check valve |
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| Publication number | Publication date |
|---|---|
| CN106352155B (en) | 2018-06-19 |
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