CN106352155B - One loop of nuclear power station non-return valve on-line pressure sealant repair method - Google Patents
One loop of nuclear power station non-return valve on-line pressure sealant repair method Download PDFInfo
- Publication number
- CN106352155B CN106352155B CN201610848380.3A CN201610848380A CN106352155B CN 106352155 B CN106352155 B CN 106352155B CN 201610848380 A CN201610848380 A CN 201610848380A CN 106352155 B CN106352155 B CN 106352155B
- Authority
- CN
- China
- Prior art keywords
- valve
- return valve
- flap
- power station
- nuclear power
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Classifications
-
- 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
Landscapes
- 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 present invention relates to nuclear power station technical fields, more particularly to a kind of one loop of nuclear power station non-return valve on-line pressure sealant repair method, innovative overhauls in the cooling water in avoiding primary Ioops system less than the isolation completed in the case of low low water level to valve, since the cooling water in primary Ioops system in maintenance process is consistently higher than low low water level, then avoid the water-filling steps of exhausting that unit was vented or vacuumizes into action in startup stage, it is truly realized to primary Ioops valve without low low water level overhaul, maintenance manpower is saved, material resources cost, be conducive to greatly shorten maintenance duration, reduce the cost of overhaul.
Description
Technical field
The present invention relates to nuclear power station technical fields, 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 thermal energy released using nuclear fission
Water is heated, is then generated electricity using the Steam Actuation steam turbine generator of formation, thermal energy is converted to the process of electric energy.
Nuclear fission carries out in reactor assembly and generates energy, and water is heated by above-mentioned energy and the steaming using generation
The process that vapour pushes steam turbine generator to generate electricity carries out outside reactor assembly, and therefore, it is necessary to by the way of certain
Transferring out for the energy security that nuclear fission in reactor assembly is generated comes.
Existing nuclear power station generally use primary Ioops system will generate energy by the way of energy exchange in reactor assembly
Amount conduction is to outside, specifically：The reactor core of reactor assembly generates huge thermal energy using fuel fission, and heap is pumped by main pump
The energy of the cooling water absorption heap in-core of core exports after being heated from heap in-core, absorbs the coolant flow after energy through steam generation
Heat transfer U-tube in device, transfers thermal energy to the secondary circuit cooling water outside U-tube by tube wall, discharges after heat again by main pump
It sends reactor core back to and re-starts energy exchange, steam generator is again introduced into after output and carries out energy exchange, cooling water is so continuous
Ground recycles in closed circuit, constantly comes out the energy conduction that reactor core nuclear fission generates, and is referred to as primary Ioops system.
During nuclear power station is run, the cooling water in primary Ioops system should be always in operation and satisfaction one
Fixed water level requirement, the primary Ioops cooling water water level for meeting the minimum requirements of nuclear power station trouble-free operation are known as low low water level.If
By the cooling water draining in primary Ioops system to less than low low water level, then unit just must be into action exhaust or pumping in startup stage
Vacuum so, will cause the increase of the extension and the cost of overhaul of overhaul duration.
Various separation valve doors are connected in primary Ioops system, including the low low water level valve of similar D2RCP320VP,
The normal isolation maintenance of such valve can be carried out in low low water level, but since the valve is in unit descending phase PT experiments
Unqualified probability is very big, according to related specifications, once PT experiments are unqualified, it is necessary to the valve repaired to ensure valve
Leakproofness, the repair stage must then empty the cooling water at the valve, thus, can result in cold in primary Ioops system
But water is less than low low water level, causes the extension of overhaul duration and the increase of the cost of overhaul, and since nuclear power station maintenance duration is tight, such as
The cooling water in primary Ioops system is where avoided to be overhauled less than the isolation completed in the case of low low water level to valve, becomes pendulum and exists
A difficult problem in face of testing staff.
Invention content
The present invention provides a kind of cooling water in primary Ioops system is avoided and is less than for problems of the prior art
The method for completing to overhaul the isolation of valve in the case of low low water level, has saved maintenance human and material resources cost, has been conducive to shorten
Maintenance duration.
The purpose that the invention is realized by the following technical scheme：
One loop of nuclear power station non-return valve on-line pressure sealant repair method, includes the following steps：
A, to setting isolation protecting device around the non-return valve of Awaiting Overhaul, primary Ioops cooling water leakage in maintenance process is prevented
Into environment；
B, primary Ioops systematic water level is controlled, primary Ioops systematic water level is dropped into the left sides of 50mm below the valve deck position of non-return valve
It is right；
C, it slowly unclamps valve deck and confirms that water level meets maintenance requirement, the isolation protecting device is collected to overflow from non-return valve opening
The primary Ioops cooling water gone out；
D, it dismantles flap bolt and removes the flap of non-return valve and overhaul, using sealing-plug to the company in non-return valve downstream
Primary Ioops supervisor's channel is connect to be blocked, and confirm and block leakproofness qualification；
E, the primary Ioops cooling water in non-return valve upstream and valve chamber is emptied；
F, installation valve seat grinder tool is ground valve seat, returns dress flap, does valve tightness experiment and switch test
It is verified；
G, after the completion of valve upkeep operation, clearing valve intracavitary portion foreign matter is filled with primary Ioops cooling water into valve chamber to being higher than
The water level of low low water level；
H, sealing-plug is removed from non-return valve downstream passage and is taken out from valve chamber；
I, gasket and valve deck are installed, and remove isolation protecting device.
Wherein, the isolation protecting device is disposed around the periphery of non-return valve, and positioned at the lower section of non-return valve opening, it is described every
From the drainpipe being also associated on protective device for discharging cooling water, which contains reservoir with cooling water.
Wherein, the water level at the valve deck of non-return valve is higher than the low low water level of primary Ioops system.
Further, it before the step d carries out disassembling section to flap, further includes verification flap and shows with the presence or absence of bite
As and detection flap and valve body both sides between have a gapless, the size control in gap is in 0.5~2mm, to the maintenance packet of flap
Include flap decontamination and flap grinding.
Wherein, in the step d, after being blocked using sealing-plug to non-return valve downstream passage, seal pressure is established, it will
Non-return valve cools down water segregation with primary Ioops.
Wherein, volume expansion after the sealing-plug inflation, establishes seal pressure, under non-return valve by the sealing-plug of expansion
Trip channel is blocked.
Wherein, the step f is specially：First, valve chamber decontamination is carried out, checks that flap and valve seat have zero defect；Then, it grinds
Valve grinding valve and valve seat；Finally, blue oil test is carried out after flap is mounted on valve seat.
Further, upkeep operation is carried out to valve and further includes seal tightness test, installed on non-return valve and suppress tool pair
The leakproofness of valve is verified, flap is dismantled and taken out again after seal tightness test qualification.
As a preferred option, check that flap and valve seat have zero defect by dyeing inspection mode.
Wherein, the sealing-plug includes cock body, and the periphery of cock body offers arc groove, offered on cock body recessed with circular arc
The medium channel of slot connection, is embedded with sealing joint strip in the arc groove, the opening of the medium channel is connected with medium
Pipeline, further includes the positioning component for being positioned to cock body, and the positioning component is connect by a screw rod with cock body.
Relative to the prior art, beneficial effects of the present invention are：
The one loop of nuclear power station non-return valve on-line pressure sealant repair method of the present invention, it is innovative in primary Ioops system is avoided
Cooling water overhauled less than the isolation completed in the case of low low water level to valve, due in primary Ioops system in maintenance process
Cooling water is consistently higher than low low water level, then avoids unit and be vented step into action exhaust or the water-filling vacuumized in startup stage
Suddenly, it is truly realized to primary Ioops valve without low low water level overhaul, has saved maintenance human and material resources cost, be conducive to significantly
Shorten maintenance duration, reduce the cost of overhaul.
Description of the drawings
Fig. 1 is the schematic diagram that isolation protecting device is set around non-return valve.
Fig. 2 unclamps valve deck and carries out the hydrophobic schematic diagram of pressure release.
Fig. 3 is to dismantle valve deck and remove the schematic diagram that flap is overhauled.
Fig. 4 is the schematic diagram blocked using sealing-plug to non-return valve downstream passage.
Fig. 5 is cooling water, the schematic diagram to valve upkeep operation and clearing valve intracavitary portion foreign matter of exhaust-valve intracavitary.
Fig. 6 is the schematic diagram that cooling water is filled with into valve chamber.
Fig. 7 is the schematic diagram removed sealing-plug, install flap.
Fig. 8 is to install valve deck, 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 bodies, 2- valve decks, 3- isolation protecting devices, 4- drainpipes, 5- flaps, 6- sealing-plugs, 61- cock bodys,
62- arc grooves, 63- sealing joint strips, 64- medium pipelines, 7- cooling waters, 8- positioning components, 9- screw rods, 10- experiment valve decks,
11- consoles, 12- pressure pumps.
Specific embodiment
Below in conjunction with drawings and the specific embodiments, the present invention will be described in detail.
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
The preparation of some row is carried out before repairing, the non-return valve upstream line of Awaiting Overhaul is isolated, does not empty medium, downstream primary Ioops water
In prescribed limit, scene prepares construction and prepares corresponding tool, specifically comprises the following steps for position control：
A, to setting isolation protecting device 3 around the non-return valve of Awaiting Overhaul, prevent cooling water 7 in maintenance process from leaking to ring
In border；The isolation protecting device 3 is disposed around the periphery of non-return valve, and be fixed on non-return valve opening lower section, for collect from
The cooling water 7 that non-return valve opening is overflowed is also associated with the drainpipe for discharging cooling water 7 on the isolation protecting device 3
4, which contains reservoir with cooling water 7；
B, control primary Ioops systematic water level, by primary Ioops systematic water level drop to non-return valve 2 position of valve deck (non-return valve
Water level at valve deck 2 is higher than the low low water level of primary Ioops system), cooling water 7 after unclamping valve deck 2 is avoided to spray；
C, release valve deck 2 progress pressure release is hydrophobic, and the isolation protecting device 3 collects the cooling water overflowed from non-return valve opening
7, and pass through drainpipe 4 cooling water 7 is delivered to cooling water 7 and contain container；
Further include verification flap 5 has gapless with the presence or absence of between 1 both sides of bite phenomenon and detection flap 5 and valve body,
The size in gap is controlled in 0.5~2mm；
D, it dismantles 5 bolt of flap and removes the flap 5 of non-return valve and overhaul, the maintenance of flap 5 is gone including flap 5
Dirty and flap 5 is ground；
Non-return valve downstream passage is blocked using sealing-plug 6 and positioning component 8, establishes seal pressure, to non-return valve
Downstream passage is blocked, and non-return valve is isolated with primary Ioops cooling water 7；
E, empty non-return valve valve chamber in cooling water 7, ensure valve chamber inside anhydrous state, and to the decontamination of valve chamber inside at
Reason；
F, installation experiment valve deck 10 carries out upkeep operation to valve, first, valve chamber decontamination is carried out, by dyeing inspection side
Formula checks that flap 5 and valve seat have zero defect；Then, flap 5 and valve seat are ground；Finally, it is carried out after flap 5 is mounted on valve seat
Blue oil test；
As shown in Figure 10, upkeep operation is carried out to valve and further includes seal tightness test, installed on non-return valve and suppress tool,
Joint test console 11 and pressure pump 12 verify the leakproofness of valve, again by flap 5 after seal tightness test qualification
It dismantles and takes out；
G, after the completion of upkeep operation, clearing valve intracavitary portion foreign matter checks 2 sealing surface of valve deck, is filled with and is configured into valve chamber
Boron water, flood to 5 installation bolt of flap；
H, confirm primary Ioops water level within the limits prescribed, pressure release simultaneously removes sealing-plug 6, and installs fixed flap 5；
I, valve deck 2 is installed, 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
Slot 62 offers the medium channel connected with arc groove 62 on cock body 61, sealing joint strip is embedded in the arc groove 62
63, the opening of the medium channel is connected with medium pipeline 64, further includes the positioning component for being positioned to cock body 61
8, the positioning component 8 is connect by a screw rod 9 with cock body 61.
Embodiment described above only expresses the several embodiments of the present invention, and description is more specific and detailed, but simultaneously
Cannot the limitation to the scope of the claims of the present invention therefore 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, various modifications and improvements can be made, these belong to the guarantor of the present invention
Protect range.Therefore, the protection domain of patent of the present invention should be determined by the appended claims.
Claims (10)
1. one loop of nuclear power station non-return valve on-line pressure sealant repair method, which is characterized in that include the following steps：
A, to setting isolation protecting device around the non-return valve of Awaiting Overhaul, primary Ioops cooling water leakage is prevented in maintenance process to ring
In border；
B, primary Ioops systematic water level is controlled, primary Ioops systematic water level is dropped into 50mm or so below the valve deck position of non-return valve；
C, it slowly unclamps valve deck and confirms that water level meets maintenance requirement, the isolation protecting device collects what is overflowed from non-return valve opening
Primary Ioops cooling water；
D, it dismantles flap bolt and removes the flap of non-return valve and overhaul, utilize connection one of the sealing-plug to non-return valve downstream
Supervisor's channel in circuit is blocked, and is confirmed and blocked leakproofness qualification；
E, the primary Ioops cooling water in non-return valve upstream and valve chamber is emptied；
F, installation valve seat grinder tool is ground valve seat, returns dress flap, does valve tightness experiment and switch test carries out
Verification；
G, after the completion of valve upkeep operation, clearing valve intracavitary portion foreign matter is filled with primary Ioops cooling water into valve chamber to higher than low
The water level of water level；
H, sealing-plug is removed from non-return valve downstream passage and is taken out from valve chamber；
I, gasket and valve deck are installed, 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, which is characterized in that it is described every
From the periphery that protective device is disposed around non-return valve, and it is also connected on the lower section of non-return valve opening, the isolation protecting device
The drainpipe of discharge cooling water is useful for, which contains reservoir with cooling water.
3. one loop of nuclear power station non-return valve on-line pressure sealant repair method according to claim 1, which is characterized in that the step
In rapid b, the water level at the valve deck 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, which is characterized in that the step
Before rapid d carries out disassembling section to flap, verification flap is further included with the presence or absence of bite phenomenon and detection flap and valve body both sides
Between have a gapless, the size control in gap includes flap decontamination to the maintenance of flap and flap is ground in 0.5~2mm.
5. one loop of nuclear power station non-return valve on-line pressure sealant repair method according to claim 1, which is characterized in that the step
In rapid d, after being blocked using sealing-plug to non-return valve downstream passage, seal pressure is established, non-return valve and primary Ioops are cooled down
Water segregation.
6. one loop of nuclear power station non-return valve on-line pressure sealant repair method according to claim 5, which is characterized in that described close
Volume expansion after blocking inflation, establishes seal pressure by the sealing-plug of expansion, 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, which is characterized in that the step
Suddenly f is specially：First, valve chamber decontamination is carried out, checks that flap and valve seat have zero defect；Then, flap and valve seat are ground；Finally,
Blue oil test is carried out after flap is mounted on valve seat.
8. one loop of nuclear power station non-return valve on-line pressure sealant repair method according to claim 7, which is characterized in that valve
Carry out upkeep operation and further include seal tightness test, on non-return valve installation suppress tool the leakproofness of valve verified, it is close
Flap is dismantled and taken out again after envelope property pass the test.
9. one loop of nuclear power station non-return valve on-line pressure sealant repair method according to claim 7, which is characterized in that by
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, which is characterized in that described
Sealing-plug includes cock body, and the periphery of cock body offers arc groove, the medium channel connected with arc groove is offered on cock body,
Sealing joint strip is embedded in the arc groove, the opening of the medium channel is connected with medium pipeline, further include for pair
The positioning component that cock body is positioned, the positioning component are connect by a screw rod with cock body.
Priority Applications (1)
| 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 |
Applications Claiming Priority (1)
| 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 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN106352155A CN106352155A (en) | 2017-01-25 |
| CN106352155B true CN106352155B (en) | 2018-06-19 |
Family
ID=57859276
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201610848380.3A Active CN106352155B (en) | 2016-09-23 | 2016-09-23 | One loop of nuclear power station non-return valve on-line pressure sealant repair method |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN106352155B (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107179169B (en) * | 2017-06-14 | 2019-05-17 | 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 |
Citations (4)
| 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 |
| 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 |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR101077230B1 (en) * | 2009-11-03 | 2011-10-28 | 한국과학기술원 | Integrated process for water-hydrogen-electricity nuclear gas-cooled reactor |
-
2016
- 2016-09-23 CN CN201610848380.3A patent/CN106352155B/en active Active
Patent Citations (4)
| 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 |
| 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 |
Also Published As
| Publication number | Publication date |
|---|---|
| CN106352155A (en) | 2017-01-25 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US11646123B2 (en) | Three-way valve operational to both transfer steam to a decontamination water tank under one accident situation and discharge the steam to atmosphere under a different accident situation | |
| CN102903404B (en) | The reactor core surplus heat of the active and non-active combination of a kind of nuclear power station discharges system | |
| CN106352155B (en) | One loop of nuclear power station non-return valve on-line pressure sealant repair method | |
| CN104538068B (en) | A kind of method that steam generator spill-over is prevented under shape pipe breaking accident operating mode of conducting heat | |
| KR20100072375A (en) | Passive emergency feedwater system for a nuclear reactor | |
| CN102831942A (en) | Emergency cooling system of spent fuel pool of nuclear power station | |
| KR101040809B1 (en) | Sealing Test Device for Motor Actuation Parallel Gate Valve on Reactor Coolant System | |
| CN109855814B (en) | Method and system for detecting tightness of RCPB isolation valve of nuclear power plant | |
| CN105157923B (en) | Method for testing tightness of isolation valve group at inlet and outlet of containment closed loop | |
| KR20200073162A (en) | Depressurisation valve | |
| KR100942194B1 (en) | Apparatus for draining of RCS and the method there for | |
| CN106373623B (en) | The detection method of nuclear power plant reactor residual heat removal system leakage | |
| CN205541969U (en) | Active protection system of PWR non - and pressure differential valve of relying on oneself | |
| CN203397707U (en) | Security defending system for nuclear power station | |
| KR20170098222A (en) | Method for managing stoppage of a pressurised-water nuclear reactor | |
| CN112325491B (en) | Water circulation test method for tower type photo-thermal power station | |
| CN104112481B (en) | Reduce accident source term release device | |
| CN106382412B (en) | On-line pressure sealant method is leaked in one loop of nuclear power station smaller diameter valve | |
| KR20180079990A (en) | Nuclear Power Plant having a passive core cooling function during loss of AC power | |
| Pla et al. | Simulation of steam generator plugging tubes in a PWR to analyze the operating impact | |
| KR20200119703A (en) | system for reducing the release of radioactive material to the atmosphere under severe accident | |
| CN110196216A (en) | No. three sealing filter test methods of main pump, system and device | |
| CN111521352A (en) | Nuclear power station unit check valve sealing performance detection and exception handling method | |
| Pla et al. | Analysis of steam generator tube plugging in A PWR. influence in the emergency operating procedures | |
| CN103733268B (en) | For the treatment of the equipment of the fuel stick of the melting in nuclear reactor |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |