CN113279977A - Nuclear power station main pump second shaft seal leakage flow monitoring and intervention method - Google Patents
Nuclear power station main pump second shaft seal leakage flow monitoring and intervention method Download PDFInfo
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- CN113279977A CN113279977A CN202110550591.XA CN202110550591A CN113279977A CN 113279977 A CN113279977 A CN 113279977A CN 202110550591 A CN202110550591 A CN 202110550591A CN 113279977 A CN113279977 A CN 113279977A
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- 238000000034 method Methods 0.000 title claims abstract description 40
- 238000012544 monitoring process Methods 0.000 title claims abstract description 38
- 238000012423 maintenance Methods 0.000 claims abstract description 39
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 9
- 230000008569 process Effects 0.000 abstract description 10
- 238000012954 risk control Methods 0.000 abstract description 3
- 238000007789 sealing Methods 0.000 description 9
- 230000003068 static effect Effects 0.000 description 5
- 238000002347 injection Methods 0.000 description 4
- 239000007924 injection Substances 0.000 description 4
- 230000003203 everyday effect Effects 0.000 description 3
- 230000000630 rising effect Effects 0.000 description 3
- 230000008901 benefit Effects 0.000 description 2
- 230000033228 biological regulation Effects 0.000 description 2
- 230000008859 change Effects 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 239000010935 stainless steel Substances 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000006978 adaptation Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- UFGZSIPAQKLCGR-UHFFFAOYSA-N chromium carbide Chemical compound [Cr]#C[Cr]C#[Cr] UFGZSIPAQKLCGR-UHFFFAOYSA-N 0.000 description 1
- 238000012790 confirmation Methods 0.000 description 1
- 230000009849 deactivation Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000006073 displacement reaction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 229910002804 graphite Inorganic materials 0.000 description 1
- 239000010439 graphite Substances 0.000 description 1
- 238000011065 in-situ storage Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000000243 solution Substances 0.000 description 1
- 230000006641 stabilisation Effects 0.000 description 1
- 238000011105 stabilization Methods 0.000 description 1
- 229910003470 tongbaite Inorganic materials 0.000 description 1
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Classifications
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F04—POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
- F04D—NON-POSITIVE-DISPLACEMENT PUMPS
- F04D15/00—Control, e.g. regulation, of pumps, pumping installations or systems
- F04D15/0077—Safety measures
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F04—POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
- F04D—NON-POSITIVE-DISPLACEMENT PUMPS
- F04D15/00—Control, e.g. regulation, of pumps, pumping installations or systems
- F04D15/02—Stopping of pumps, or operating valves, on occurrence of unwanted conditions
- F04D15/0245—Stopping of pumps, or operating valves, on occurrence of unwanted conditions responsive to a condition of the pump
- F04D15/0263—Stopping of pumps, or operating valves, on occurrence of unwanted conditions responsive to a condition of the pump the condition being temperature, ingress of humidity or leakage
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F04—POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
- F04D—NON-POSITIVE-DISPLACEMENT PUMPS
- F04D29/00—Details, component parts, or accessories
- F04D29/08—Sealings
- F04D29/10—Shaft sealings
- F04D29/12—Shaft sealings using sealing-rings
- F04D29/126—Shaft sealings using sealing-rings especially adapted for liquid pumps
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Structures Of Non-Positive Displacement Pumps (AREA)
Abstract
The invention discloses a method for monitoring and intervening the leakage flow of a second main pump shaft seal of a nuclear power station, which comprises the following steps of S1, collecting leakage flow data, wherein the leakage flow data comprises an average value of the second main pump leakage flow and a stable value of the second main pump leakage flow; s2, judging whether the average value of the leakage flow of the second main pump of any one main pump exceeds a monitoring threshold, if so, executing S3, and if not, returning to S1; s3, judging whether the leakage data meet a pump stopping maintenance condition, if so, outputting a pump stopping maintenance instruction, and if not, returning to S2; the pump stopping maintenance condition comprises that the average value of the leakage flow of the second main pump exceeds a pump stopping threshold; s4, judging whether the leakage flow stability value of the second main pump exceeds an intervention threshold value or not, and if so, executing intervention operation; if not, the process returns to S3. The method for monitoring and intervening the leakage flow of the second shaft seal of the main pump of the nuclear power station saves the excessive labor input and the increased maintenance cost caused by excessive maintenance of the shaft seal of the main pump, and improves the risk control capability of safe operation of the main pump of the nuclear power station.
Description
Technical Field
The invention relates to the field of nuclear power plants, in particular to a method for monitoring and intervening leakage flow of a second shaft seal of a main pump of a nuclear power plant.
Background
A reactor main pump of a certain nuclear power plant in China is a 100-type main pump, and the 100-type main pump is a vertical single-stage centrifugal pump produced by FDJV (Toyokusho Matong) company and is provided with a controllable leakage shaft seal device. When the main pump works normally, the main pump works under the absolute pressure of 15.5MPa and the temperature of 292 ℃, and a special shaft seal device is arranged for preventing the leakage of high-temperature, high-pressure and radioactive coolant. The shaft seal device adopts three shaft seals, leakage can be controlled, and the radioactive coolant can be prevented from leaking into the containment.
The second shaft seal of the main pump is a friction surface type shaft seal, which consists of a stainless steel static ring covered by graphite and a stainless steel dynamic ring coated with chromium carbide and rotating together with the shaft. The static ring is pressed on the dynamic ring by fluid pressure and spring force, and the friction surface between the dynamic ring and the static ring is lubricated and cooled by a small part of leakage flow of the first shaft seal. The normal leakage through the shaft seal number two is 11.4L/h, the differential pressure is 0.17MPa, and the leakage water is discharged to RCP009 BA.
The second shaft seal has the ability to withstand the operating pressures of the RCP system, so its other function is to act as a backup shaft seal in the event of a failure of the first shaft seal. If the first shaft seal is damaged, no matter the main pump is in a rotating state or a static state, the second shaft seal can replace the first shaft seal for a short time under the pressure of the RCP system. When the first shaft seal is damaged, the main control chamber indicates and gives an alarm that the first shaft seal has high leakage, an operator closes the first shaft seal leakage valve, all leakage of the first shaft seal passes through the second shaft seal, and the second shaft seal is used as a main shaft seal. The plant is then shut down in a normal sequence to replace the damaged shaft seal. And judging whether the shaft seal is damaged or not according to whether the leakage flow of the second shaft seal is abnormal or not. Under the condition of No. two shaft seal faults, the main pump can keep running as long as the pump bearing does not vibrate abnormally.
At present, a certain nuclear power station has the problem of high leakage rate of a second main pump shaft seal for a long time, the leakage rate of the second main pump shaft seal is increased to influence the leakage rate of a primary circuit, and if the leakage rate of the primary circuit exceeds the standard, a unit is withdrawn; meanwhile, if the leakage amount of the second seal continuously rises and cannot interfere, the leakage amount of the second seal of the main pump is sent out when the leakage amount of the second seal reaches 110L/h, and the first seal enters the procedure I. When the leakage amount of the second shaft seal of the main pump reaches 250L/h or more, the function of replacing the first seal for a short time is lost, and the forced manual pump stop can be caused. Therefore, the problem that the leakage quantity of the second shaft seal of the main pump is higher is an urgent need to be solved.
Disclosure of Invention
The invention aims to solve the technical problems that an improved method for monitoring and intervening the leakage flow of a second shaft seal of a main pump of a nuclear power station is provided aiming at overcoming the defects in the prior art, and the problem that forced manual pump stop of the main pump is possibly caused by high leakage amount of the second shaft seal of the main pump of a 100-type nuclear power station is solved.
The technical scheme adopted by the invention for solving the technical problems is as follows: the method for monitoring and intervening the leakage flow of the second shaft seal of the main pump of the nuclear power station comprises the following steps
S1, leakage flow data are collected, wherein the leakage flow data comprise a second main pump leakage flow average value and a second main pump leakage flow stable value;
s2, judging whether the average value of the second leakage flow of the main pump of any one main pump exceeds a monitoring threshold, if so, executing a step S3, otherwise, returning to the step S1;
s3, judging whether the leakage data meet a pump stopping maintenance condition, if so, outputting a pump stopping maintenance instruction, and if not, returning to the step S2; the pump stopping maintenance condition comprises that the average value of the second leakage flow of the main pump exceeds a pump stopping threshold;
s4, judging whether the leakage flow stability value of the second main pump exceeds an intervention threshold value or not, and if so, executing intervention operation; if not, the process returns to the step S3.
Preferably, the step S3 includes
S31, judging whether the average leakage flow of the second main pump is larger than or equal to 110L/h, if so, outputting an early warning time calculation instruction, and executing a step S32; if not, returning to the step S2;
s32, judging whether the leakage data meet the pump stopping maintenance condition or not, and if so, outputting a pump stopping maintenance instruction; if not, the process returns to step S31.
Preferably, the pump shutdown maintenance condition includes that the average leakage flow of the second main pump is more than or equal to 200L/h, and the rising rate or fluctuation of the average leakage flow of the second main pump is abnormally increased; and/or the pump stopping maintenance condition comprises that the average value of the second leakage flow of the main pump is more than or equal to 250L/h.
Preferably, the pump stop threshold is 200L/h.
Preferably, the step S4 includes the following steps:
s41, judging whether the second leakage flow stability value of the main pump of any main pump exceeds the intervention threshold value, if so, executing a step S42; if not, returning to the step S3;
s42, performing intervention operation, wherein the intervention operation comprises a main pump second shaft seal pressure difference changing operation;
s43, judging whether the leakage flow stability values of the second main pumps of all the main pumps are lower than the intervention threshold value or not, and if so, ending the intervention; if not, the process returns to the step S42.
Preferably, the intervention operation further comprises a main pump first shaft seal injection water flow adjusting operation, and/or the intervention operation further comprises a main pump top shaft oil pump operation which is repeatedly started continuously for multiple times, and/or the intervention operation further comprises a double pump starting operation, and/or the intervention operation further comprises an air compressor starting operation.
Preferably, the intervention threshold is 90L/h.
Preferably, the method further comprises step S5: judging whether the leakage flow data meets an ending condition, if so, ending, otherwise, returning to the step S2; the end condition includes that the main pump No. two leakage flow steady value of all the main pumps is lower than the monitoring threshold.
Preferably, in step S5, the ending condition further includes: the leakage flow stability value of all the second main pumps is less than or equal to 50L/h, and the duration time exceeds 30 days; and/or outputting the pump stopping maintenance instruction.
Preferably, the monitoring threshold is 50L/h.
The beneficial effects of the implementation of the invention are as follows: in the method for monitoring and intervening the leakage flow of the second shaft seal of the main pump of the nuclear power station, whether leakage data meets the pump stopping overhaul condition and the intervening threshold value is judged by setting the pump stopping overhaul condition and the intervening threshold value, so that different operations are given according to different conditions: outputting a pump stopping maintenance instruction or executing an intervention operation. Compared with the prior art which is processed according to experience, the method saves the investment of excessive manpower and the maintenance cost increased by overhauling the main pump shaft seal, and improves the risk control capability of the safe operation of the main pump of the nuclear power station.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a flow chart of a method for monitoring and intervening the leakage flow of a second shaft seal of a main pump of a nuclear power plant according to some embodiments of the invention;
FIG. 2 is a flowchart of step S3 in FIG. 1;
FIG. 3 is a flowchart of step S4 in FIG. 1;
fig. 4 is a flowchart of S5 in the method for monitoring and intervening the leakage flow of the shaft seal of the second main pump of the nuclear power plant according to other embodiments of the present invention.
Detailed Description
For a more clear understanding of the technical features, objects and effects of the present invention, embodiments of the present invention will now be described in detail with reference to the accompanying drawings.
Fig. 1 shows a method for monitoring and intervening a leakage flow of a second shaft seal of a main pump of a nuclear power plant in some embodiments of the present invention, which is used for setting a pump shutdown overhaul condition and an intervention threshold, and determining whether leakage data meets the pump shutdown overhaul condition and the intervention threshold, so as to perform different operations according to different conditions: outputting a pump stopping maintenance instruction or executing an intervention operation.
The method for monitoring and intervening the leakage flow of the second shaft seal of the main pump of the nuclear power station in the embodiment of the invention comprises the steps S1-S4, wherein the step S1 is an acquisition step for acquiring leakage flow data; s2 is a monitoring step for judging whether a monitoring threshold is exceeded and selectively starting the step S3; s3 is a pump shutdown maintenance judgment step for judging whether a pump shutdown maintenance condition is satisfied and selectively outputting a pump shutdown maintenance instruction; s4 is an intervention judging step for judging whether the stabilized value of the leakage flow rate of the second main pump exceeds an intervention threshold value, and selectively performing an intervention operation.
In step S1, leakage flow data is collected, where the leakage flow data includes an average leakage flow value of the main pump and a stable leakage flow value of the main pump.
In some embodiments, the setting of step S1 is to confirm that the leakage flow rate of the second signal is really high, and specific confirmation methods may include, but are not limited to, the following:
1. confirming the wide and narrow range reading of the second sealing leakage flow of the main pump;
2. confirming the trend of the leakage flow of the first seal of the corresponding main pump and comparing the trend with the other two main pumps;
3. confirming RPE001BA liquid level changes;
4. confirming the change of the leakage rate of the primary circuit;
5. confirm the field in-situ MD reading (if necessary).
In step S2, it is determined whether the average leakage flow rate of the second main pump of any one of the main pumps exceeds a monitoring threshold, if yes, step S3 is executed, and if no, step S1 is returned. Preferably, the monitoring threshold is 50L/h. Alternatively, the monitoring threshold may be 60-70L/h.
It will be appreciated that the benefit of setting step S2 is that the pre-arranged start-up criteria are set: when the stable value of the second sealing leakage flow of any one of the three main pumps reaches 50L/h, a plan is started. And the following plan measures are executed according to steps according to the actual situation.
In step S3, it is determined whether the leakage data satisfies a pump shutdown maintenance condition, if yes, a pump shutdown maintenance instruction is output, and if no, the process returns to step S2; the pump-off maintenance condition comprises that the average value of the second leakage flow of the main pump exceeds a pump-off threshold value. Preferably, the pump deactivation threshold is 200L/h. Alternatively, the pump-off threshold may be 180-.
Preferably, the pump stopping maintenance condition comprises that the average leakage flow of the second main pump is more than or equal to 200L/h, and the rising rate or fluctuation of the average leakage flow of the second main pump is abnormally increased; and/or the pump stopping maintenance condition comprises that the average leakage flow of the second main pump is more than or equal to 250L/h.
As shown in fig. 1-2, in some embodiments, step S3 may further include the following steps S31-S32.
S31, judging whether the average leakage flow of the second main pump is larger than or equal to 110L/h, if so, outputting an early warning time calculation instruction, and executing the step S32; if not, the process returns to step S2.
S32, judging whether the leakage data meet the pump stopping maintenance condition, and if so, outputting a pump stopping maintenance instruction; if not, the process returns to step S31.
Specifically, when any one of the three main pumps and the second sealing leakage flow stable value reach 50L/h, a device responsible person is informed to confirm the authenticity of leakage, if the actual leakage is confirmed, the change condition of the leakage rate is monitored every day, and the monitoring contents are as follows:
(1) the second main pump seals the leakage condition of the wide-narrow range MD;
(2) the water flow injected by the first shaft seal of the main pump and the leakage flow of the first shaft seal;
(3) RPE001BA liquid level and fluctuation frequency;
(4) the conditions of the operation parameters of the pump set such as vibration and displacement of the main pump;
(5) the water replenishing trend and frequency of a third shaft seal of the main pump;
(6) fluctuation of leakage amount of the primary circuit.
The average value of the sealing leakage flow of any one of the three main pumps and the second main pump reaches 110L/h, and an early warning time calculation instruction is output, namely, a responsible person is informed to monitor every day and predict the possible time of the expected leakage flow reaching 250L/h. Alternatively, the warning time calculation instruction can also be transmitted to a calculation end, so that the calculation end monitors and estimates the time of the expected leakage flow reaching 250L/h every day.
When the average value of the second sealing leakage flow of any one of the three main pumps reaches 200L/h and the rising rate or fluctuation is abnormally increased or the average value reaches 250L/h, the pump is stopped for maintenance after decision is made.
In step S4, it is determined whether the leakage flow stability value of the main pump number two exceeds an intervention threshold, and if yes, an intervention operation is performed; if not, the process returns to step S3. Optionally, the intervention operation further comprises a main pump first shaft seal injection water flow adjusting operation, and/or the intervention operation further comprises a main pump top shaft oil pump operation which is repeatedly started continuously for multiple times, and/or the intervention operation further comprises a double pump starting operation, and/or the intervention operation further comprises an air compressor starting operation. Preferably, the intervention threshold is 90L/h. Alternatively, the intervention threshold may be 80-100L/h.
As shown in fig. 1-3, in some preferred embodiments, the step S4 may further include the following steps S41-S43.
S41, judging whether the second leakage flow stability value of the main pump of any main pump exceeds an intervention threshold value, if so, executing a step S42; if not, the process returns to step S3.
And S42, performing intervention operation, wherein the intervention operation comprises a second main pump shaft seal differential pressure changing operation.
S43, judging whether the leakage flow stability values of the second main pumps of all the main pumps are lower than an intervention threshold value or not, and if so, ending the intervention; if not, the process returns to step S42.
Specifically, when the stable value of the second sealing leakage flow of any one of the three main pumps reaches 90L/h, the equipment responsible person is informed, after the actual leakage is confirmed, the following intervention measures are sequentially executed (after any intervention scheme is executed, the leakage flow is reduced to below 90L/and then the observation is stopped)
1. The first intervention measure is a main pump second shaft seal differential pressure changing operation: and changing the differential pressure of the second shaft seal of the main pump to ensure that the sealing surface of the main pump is attached again.
The concrete measures are as follows: under the condition that the working condition of the unit is allowed, the pressure of the RCP009BA of the volume control box is reduced as much as possible; increasing RPE001BA pressure; and a small-flow isolating valve of the charging pump is isolated for a short time.
2. The intervention measure II is the operation of adjusting the flow of the water injected into the first shaft seal of the main pump: properly reducing the injection water flow of the first shaft seal of the main pump, wherein the adjustment range of the injection water flow is 1.6m3/h～2.3m3H, each adjustment amount is not more than 0.2m3/h；
3. And an intervention measure III is to continuously and repeatedly start the main pump top shaft oil pump for a plurality of times: the main pump top shaft oil pump RCP011PO is started repeatedly for a plurality of times continuously, so that shaft covers of the second shaft seal dynamic and static rings are attached again;
4. and the intervention measure four is a double-pump starting operation: and starting the RCV pump to run in a double pump mode to perform disturbance.
5. And the intervention measure five is the starting operation of the air compressor: and starting the TEG air compressor to disturb the pressure of the second sealing leakage pipeline.
Referring to fig. 1 to 4, in some embodiments of the present invention, the method for monitoring and intervening in the leakage flow of the second shaft seal of the main pump of the nuclear power plant further includes step S5: judging whether the leakage flow data meets an ending condition, if so, ending, otherwise, returning to the step S2; the end condition includes that the leakage flow stabilization value of the second main pump of all the main pumps is lower than the monitoring threshold value.
Preferably, in step S5, the ending condition further includes: the leakage flow stability value of all the second main pumps is less than or equal to 50L/h and the duration time exceeds 30 days; and/or outputting a pump shutdown maintenance instruction.
Specifically, the leakage flow of the second seal of the three main pumps is reduced to below 50L/h, the trend is stable for more than one month or the failed main pump is stopped for maintenance.
In the technical field, according to the requirements of operation regulations, after a high leakage flow alarm of a second sealing of a main pump occurs, a section 3.7 of an I regulation RCP2 needs to be executed;
i protocol (K-OP-I-3-RCP-002):
the following operations are required after the alarm of the leakage flow of the second main pump shaft seal occurs:
1. checking whether the No. 1 shaft seal leakage pipeline is isolated by mistake;
2. checking whether the No. 1 shaft seal pipeline has backflow risk or not;
3. verifying whether the No. 1 shaft seal leakage flow and the No. 2 shaft seal leakage flow are in a normal operation area or not;
4. judging whether the shaft seal device No. 2 is damaged, if the main pump does not vibrate abnormally, the pump is put into operation continuously, but the shaft seal device needs to be replaced as soon as possible;
5. servicing the main pump shaft seals requires transitioning the reactor to a maintenance shutdown mode.
Therefore, if the leakage amount of the second seal continuously rises and cannot intervene, the leakage amount of the second seal of the main pump is sent out when the leakage amount of the second seal reaches 110L/h, and the I rule is entered. Consumes a large amount of manpower and material resources and has high operation cost.
The method for monitoring and intervening the leakage flow of the second shaft seal of the main pump of the nuclear power station in the embodiment of the invention has the advantages that: compared with the prior art which is processed according to experience, the method saves the investment of excessive manpower and the maintenance cost increased by overhauling the main pump shaft seal, and improves the risk control capability of the safe operation of the main pump of the nuclear power station.
The above description is only a preferred embodiment of the present invention, and the protection scope of the present invention is not limited to the above embodiments, and all technical solutions belonging to the idea of the present invention belong to the protection scope of the present invention. It should be noted that several modifications and adaptations to those skilled in the art without departing from the principles of the present invention should also be considered within the scope of the present invention.
Claims (10)
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| CN113898568A (en) * | 2021-10-08 | 2022-01-07 | 苏州热工研究院有限公司 | A test method for the reliability evaluation of the No. 1 seal of the main pump of nuclear power |
| CN114151362A (en) * | 2021-11-30 | 2022-03-08 | 中广核工程有限公司 | Nuclear power station main pump shaft seal leakage monitoring method and device and computer equipment |
| CN116201722A (en) * | 2021-11-30 | 2023-06-02 | 福建福清核电有限公司 | Nuclear power station main pump mechanical seal leakage high fault relief method |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN113898568A (en) * | 2021-10-08 | 2022-01-07 | 苏州热工研究院有限公司 | A test method for the reliability evaluation of the No. 1 seal of the main pump of nuclear power |
| CN114151362A (en) * | 2021-11-30 | 2022-03-08 | 中广核工程有限公司 | Nuclear power station main pump shaft seal leakage monitoring method and device and computer equipment |
| CN116201722A (en) * | 2021-11-30 | 2023-06-02 | 福建福清核电有限公司 | Nuclear power station main pump mechanical seal leakage high fault relief method |
| CN114151362B (en) * | 2021-11-30 | 2023-09-22 | 中广核工程有限公司 | Nuclear power station main pump shaft seal leakage monitoring method, device and computer equipment |
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