CN117703843A - Vacuumizing device of primary loop system of nuclear power plant reactor and water filling method thereof - Google Patents
Vacuumizing device of primary loop system of nuclear power plant reactor and water filling method thereof Download PDFInfo
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- CN117703843A CN117703843A CN202311750508.9A CN202311750508A CN117703843A CN 117703843 A CN117703843 A CN 117703843A CN 202311750508 A CN202311750508 A CN 202311750508A CN 117703843 A CN117703843 A CN 117703843A
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 48
- 238000011049 filling Methods 0.000 title claims abstract description 18
- 238000000034 method Methods 0.000 title claims abstract description 18
- 239000003381 stabilizer Substances 0.000 claims abstract description 34
- 238000005086 pumping Methods 0.000 claims abstract description 17
- 238000007789 sealing Methods 0.000 claims abstract description 15
- 238000000605 extraction Methods 0.000 claims description 16
- 239000002184 metal Substances 0.000 claims description 7
- 238000004804 winding Methods 0.000 claims description 3
- 238000011068 loading method Methods 0.000 claims description 2
- 230000003068 static effect Effects 0.000 abstract description 6
- 239000012530 fluid Substances 0.000 description 12
- 239000002826 coolant Substances 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 238000013461 design Methods 0.000 description 3
- 238000002347 injection Methods 0.000 description 3
- 239000007924 injection Substances 0.000 description 3
- 238000012546 transfer Methods 0.000 description 3
- 230000000740 bleeding effect Effects 0.000 description 2
- 230000006872 improvement Effects 0.000 description 2
- 238000002156 mixing Methods 0.000 description 2
- 238000009423 ventilation Methods 0.000 description 2
- 208000035874 Excoriation Diseases 0.000 description 1
- 238000005299 abrasion Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 230000006835 compression Effects 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 230000002265 prevention Effects 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 239000000243 solution Substances 0.000 description 1
- 238000005507 spraying Methods 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
Classifications
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F04—POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
- F04F—PUMPING OF FLUID BY DIRECT CONTACT OF ANOTHER FLUID OR BY USING INERTIA OF FLUID TO BE PUMPED; SIPHONS
- F04F5/00—Jet pumps, i.e. devices in which flow is induced by pressure drop caused by velocity of another fluid flow
- F04F5/14—Jet pumps, i.e. devices in which flow is induced by pressure drop caused by velocity of another fluid flow the inducing fluid being elastic fluid
- F04F5/16—Jet pumps, i.e. devices in which flow is induced by pressure drop caused by velocity of another fluid flow the inducing fluid being elastic fluid displacing elastic fluids
- F04F5/20—Jet pumps, i.e. devices in which flow is induced by pressure drop caused by velocity of another fluid flow the inducing fluid being elastic fluid displacing elastic fluids for evacuating
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F04—POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
- F04F—PUMPING OF FLUID BY DIRECT CONTACT OF ANOTHER FLUID OR BY USING INERTIA OF FLUID TO BE PUMPED; SIPHONS
- F04F5/00—Jet pumps, i.e. devices in which flow is induced by pressure drop caused by velocity of another fluid flow
- F04F5/44—Component parts, details, or accessories not provided for in, or of interest apart from, groups F04F5/02 - F04F5/42
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F04—POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
- F04F—PUMPING OF FLUID BY DIRECT CONTACT OF ANOTHER FLUID OR BY USING INERTIA OF FLUID TO BE PUMPED; SIPHONS
- F04F5/00—Jet pumps, i.e. devices in which flow is induced by pressure drop caused by velocity of another fluid flow
- F04F5/44—Component parts, details, or accessories not provided for in, or of interest apart from, groups F04F5/02 - F04F5/42
- F04F5/48—Control
- F04F5/52—Control of evacuating pumps
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F04—POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
- F04F—PUMPING OF FLUID BY DIRECT CONTACT OF ANOTHER FLUID OR BY USING INERTIA OF FLUID TO BE PUMPED; SIPHONS
- F04F5/00—Jet pumps, i.e. devices in which flow is induced by pressure drop caused by velocity of another fluid flow
- F04F5/54—Installations characterised by use of jet pumps, e.g. combinations of two or more jet pumps of different type
-
- 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)
- Physics & Mathematics (AREA)
- Fluid Mechanics (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The application provides a vacuum pumping device of a nuclear power plant reactor-loop system and a water filling method thereof. One end of the vacuum ejector is connected with a compressed air system of the nuclear power plant, and the vacuum ejector is configured to extract air in a loop. The pressure vessel exhaust top cover is connected with the reactor pressure vessel in a sealing way, and a pipeline and a manual valve for breaking vacuum are arranged at the top of the pressure vessel exhaust top cover. One end of the pressure stabilizer air exhaust cover plate is connected with the other end of the vacuum ejector, and the other end of the pressure stabilizer air exhaust cover plate is connected with the pressure stabilizer manhole. By arranging the special vacuumizing device for the primary loop system of the nuclear power plant reactor, the vacuumizing device is used for reducing the air content of the primary loop during water filling, dynamic and static exhaust by the main pump is avoided, and the equipment reliability of the main pump and the economy of the nuclear power unit are improved.
Description
Technical Field
The application belongs to the technical field of nuclear power, and particularly relates to a vacuumizing device of a primary loop system of a nuclear power plant reactor and a water filling method of the vacuumizing device.
Background
Taking an M310 type nuclear power plant as an example, after a first loop system of a reactor of the M310 type nuclear power plant is discharged to a low water level, when water is refilled, air in a pipeline and equipment cannot be completely discharged out of the system through gravity due to the influence of an inverted U-shaped pipe of a steam generator and a circular top cover of a pressure vessel, and air in a main system needs to be driven through a static exhaust-dynamic exhaust-combined exhaust mode, wherein the dynamic exhaust and the combined exhaust need to sequentially click three reactor coolant pumps (hereinafter referred to as main pumps and the same).
The main pump is under the main system low pressure platform, and the auxiliary thrust tile bears the vertical downward load of the main pump axial direction. However, the top shaft oil system of the auxiliary thrust tile is not designed for a certain type of main pump, so that the auxiliary tile bears a larger load during the starting of the pump, and the risk of abrasion of the auxiliary thrust tile of the motor is larger when the low-pressure platform starts the main pump. On the other hand, the water inlet mode of the main system currently commonly adopted by the primary loop system of the nuclear power plant reactor takes longer time, and the critical path time of static exhaust, pressure rise, top shaft of the main pump, dynamic exhaust and combined exhaust is estimated to be 24 hours.
Disclosure of Invention
In view of the above, embodiments of the present application are directed to providing a vacuum pumping device for a primary loop system of a nuclear power plant reactor and a water filling method thereof, which are capable of reducing a gas content of a loop by using the vacuum pumping device when filling water by providing a dedicated vacuum pumping device for the primary loop system of the nuclear power plant reactor, so as to solve the problems of long time consumption and easy damage of the main pump caused by using the main pump to perform dynamic and static exhaust.
The first aspect of the application provides a vacuum pumping device of a nuclear power plant reactor primary loop system, which comprises a reactor pressure vessel, a voltage stabilizer, a steam generator and a main pump which are sequentially connected, wherein the vacuum pumping device comprises a vacuum ejector, a pressure vessel air exhaust top cover and a voltage stabilizer air exhaust cover plate. One end of the vacuum ejector is connected with a compressed air system of the nuclear power plant, and the vacuum ejector is configured to extract air in a loop. The pressure vessel exhaust top cover is connected with the reactor pressure vessel in a sealing way, and a pipeline and a manual valve for breaking vacuum are arranged at the top of the pressure vessel exhaust top cover. One end of the pressure stabilizer air exhaust cover plate is connected with the other end of the vacuum ejector, and the other end of the pressure stabilizer air exhaust cover plate is connected with the pressure stabilizer manhole.
In the scheme, through setting up vacuum ejector, pressure vessel top cap and stabiliser cover plate of bleeding in this evacuating device, utilize this pressure vessel top cap buckle closure pressure vessel of bleeding for nuclear power plant reactor return circuit is closed circuit, use vacuum ejector to adopt outside air space power supply to take out the interior air of return circuit, vacuum ejector's exhaust can be filtered the back through high-efficient ventilation filter, directly discharge to the containment, thereby the air content of a return circuit has been reduced, also avoided traditional nuclear power plant to utilize the main pump to carry out sound exhaust, reduce even cancel the demand that uses the main pump to carry out main system and move exhaust and joint exhaust.
In a specific implementation mode of the method, the pressure vessel air extraction top cover is contacted with the sealing surface of the pressure vessel cylinder body through a rubber sealing ring arranged at a groove of the flange surface.
In one specific implementation of the present application, the pressure vessel extraction cap is an arcuate cover plate.
In a specific implementation mode of the method, a connecting piece connected with the reactor pressure vessel is arranged on the pressure vessel air pumping top cover, and the connecting piece has looseness prevention or anti-falling performance.
In one specific implementation of the present application, a pressure regulator suction cover plate is connected to a pressure regulator manhole through bolts and metal winding pads.
A second aspect of the present application provides a method of filling water in a nuclear power plant reactor-loop system, the method comprising: closing the relevant valves and the main pump mechanical seal of the nuclear power plant reactor-loop system during the low water level of the nuclear power plant and before the reactor is charged; hoisting a pressure vessel extraction cap in a vacuum pumping device of a nuclear power plant reactor-loop system of the first aspect of the application to a reactor pressure vessel to hermetically connect the pressure vessel extraction cap with the reactor pressure vessel; fixedly mounting a pressure stabilizer air exhaust cover plate in the vacuumizing device on a pressure stabilizer manhole; one end of a vacuum ejector in the vacuumizing device is connected with a compressed air system of the nuclear power plant, and the other end of the vacuum ejector is connected with an air suction cover plate of the voltage stabilizer; filling water to the upper edge of the main pipeline which is over the loop; opening a compressed air inlet valve of the compressed air system to vacuumize so as to vacuumize a loop pressure to a preset vacuum pressure; the water is filled into the main system by opening a loop water inlet valve, and a manual valve at the air exhaust top cover of the pressure vessel is opened to break vacuum so as to press the water in the pressure vessel of the reactor into the inverted U-shaped pipe of the steam generator.
In one specific implementation of the present application, the preset vacuum pressure is 0.17bar.
Drawings
Fig. 1 is a schematic diagram of a nuclear power plant reactor loop system.
Fig. 2 is a schematic structural diagram of a vacuum pumping device of a primary loop system of a nuclear power plant reactor according to an embodiment of the present application.
Fig. 3 is a schematic flow chart of a water filling method of a primary loop system of a nuclear power plant reactor according to an embodiment of the present application.
Detailed Description
The following description of the technical solutions in the embodiments of the present application will be made clearly and completely with reference to the drawings in the embodiments of the present application, and it is apparent that the described embodiments are only some embodiments of the present application, not all embodiments. All other embodiments, which can be made by one of ordinary skill in the art without undue burden from the present disclosure, are within the scope of the present disclosure.
Fig. 1 is a schematic diagram of a nuclear power plant reactor loop system. As shown in fig. 1, the nuclear power plant reactor-loop system includes a reactor pressure vessel 1, a pressurizer 2, a steam generator 3, and a main pump 4, which are connected in this order.
It should be noted that the nuclear power plant includes, but is not limited to, an M310 type nuclear power plant. The evacuation device of the nuclear power plant reactor-loop system of the present application may be applied to any nuclear power plant reactor-loop system including a reactor pressure vessel, a pressurizer 2, a steam generator 3 and a main pump 4. The nuclear power plant reactor-loop system may also include a main pipe and other valves, etc.
The reactor pressure vessel 1 may be a cylindrical vessel with a welded hemispherical bottom head and a removable flange-attached pressure vessel C-ring seal with a hemispherical top head. The pressure vessel is used for carrying nuclear fuel, and heat energy generated by the reactor core is transferred to the outside of the pressure vessel through reactor coolant.
The voltage stabilizer 2 can be a vertical circular container, and the accurate control of the pressure of a loop is realized through the adjustment of the spraying flow of the electric heater and the voltage stabilizer.
The steam generator 3 may be constituted by a vertical cylinder with built-in steam-water separator means and an inverted U-shaped heat transfer tube bundle. The reactor coolant flows into the steam generator 3 from the inlet of the hemispherical head at the lower part of the steam generator 3, flows through the inverted U-shaped pipe and transfers heat to the feed water of the two circuits.
The main pump 4 may be the only rotating device of the reactor coolant system that absorbs heat from the pressure vessel and drives heat transfer to the steam generator 3.
Fig. 2 is a schematic structural diagram of a vacuum pumping device of a primary loop system of a nuclear power plant reactor according to an embodiment of the present application.
As shown in fig. 2, the vacuum pumping device comprises a vacuum ejector 5, a pressure vessel pumping roof 6 and a pressure stabilizer pumping cover plate 7. One end of the vacuum ejector 5 is connected to a compressed air system of the nuclear power plant, and the vacuum ejector 5 is configured to draw out air in a circuit. The pressure vessel exhaust top cover 6 is in sealing connection with the reactor pressure vessel 1, and a pipeline and a manual valve for breaking vacuum are arranged at the top of the pressure vessel exhaust top cover 6. One end of the pressure stabilizer air exhaust cover plate 7 is connected with the other end of the vacuum ejector 5, and the other end of the pressure stabilizer air exhaust cover plate 7 is connected with a pressure stabilizer manhole. In this way, through setting up vacuum ejector 5, pressure vessel top cap 6 and stabiliser cover 7 that draws air in this evacuating device, utilize this pressure vessel top cap 6 buckle closure pressure vessel that draws air in the first circuit of nuclear power plant reactor for closed circuit, use vacuum ejector 5 to adopt outside air space power supply to draw out the air in the first circuit, the exhaust of vacuum ejector 5 can directly discharge to the containment after high-efficient ventilation filter filters, thereby the air content of a circuit has been reduced, the dynamic and static exhaust of traditional nuclear power plant utilization main pump 4 has also been avoided, reduce even cancel the demand that uses main pump 4 to carry out main system and move exhaust and joint exhaust, accordingly, avoid the unusual wearing and tearing of vice tile at main system low pressure platform start-up even burn-up of main pump 4, reduce the number of times that main pump 4 starts at low pressure platform, improve the equipment reliability of main pump 4, and simultaneously show saving the overhaul time limit, the economy of nuclear power unit has been improved, the security of nuclear power unit and the reliability level of key sensitive equipment has also been improved.
Experiments prove that the vacuumizing device of the primary loop system of the nuclear power plant reactor provided by the embodiment of the application can be used for filling water, and the vacuumizing device can be used for contributing to the safety and overhaul economy of the primary pump 4 of the nuclear power plant. In terms of safety improvement, by adopting the vacuumizing device to close a loop system, vacuumizing the loop system, reducing the pressure of the system to 0.17bar, and then opening a loop water inlet valve to fill water into the main system, the requirements of using the main pump 4 for main system dynamic exhaust and combined exhaust can be reduced or even eliminated. From the aspect of economic benefit improvement, the current main system water inlet mode adopted by Fuqing nuclear power unit No. 1-4 takes longer time, and taking 303 overhaul arrangement as an example, the static exhaust-boost-main pump top shaft-dynamic exhaust-combined exhaust estimated critical path time is 23.5 hours, and the past several overhaul periods are about 20-30 hours, and the estimated time is about 5-6 hours by adopting the scheme of the embodiment of the application, so that the overhaul critical path time can be obviously shortened, and the overhaul economy of a nuclear power plant is improved.
The vacuum ejector 5 may be a pressurizing device that does not directly consume mechanical energy and has no moving parts. In the vacuum ejector 5, two fluids with different pressures are mixed with each other, energy exchange occurs, and finally a mixed fluid with middle pressure is formed, the fluid with higher pressure is called working fluid, and the fluid with lower pressure taken away is called ejection fluid. The performance of the gas injector depends on the expansion ratio of the working fluid (ratio of working fluid pressure to injection fluid pressure) and the injection fluid compression ratio (ratio of mixed fluid pressure to injection fluid pressure). For example, the main components of the vacuum ejector 5 include a working nozzle, a mixing chamber conical section, a mixing chamber cylindrical section, and a diffuser. The structure of the vacuum ejector 5 shown in fig. 2 is merely exemplary as long as the vacuuming function in the embodiment of the present application can be achieved, and on the basis of this, the embodiment of the present application does not specifically limit the structure of the vacuum ejector 5.
One end of the vacuum ejector 5 is connected with the original compressed air process system of the nuclear power plant through a quick connector and an attached metal hose, and the compressed air is used as an air source or a power source. The other end of the vacuum ejector 5 can be connected with a pressure stabilizer suction cover plate 7 through a metal hose to be used as an interface of a reactor loop.
The pressure vessel air exhaust top cover 6 is only required to be matched with the sealing surface of the pressure vessel cylinder body, and on the basis, the structural design of the pressure vessel air exhaust top cover 6 and the connection mode of the pressure vessel air exhaust top cover 6 and the pressure vessel are not particularly limited.
In at least one embodiment of the present application, the pressure vessel suction top cover 6 contacts the sealing surface of the pressure vessel cylinder body through a rubber sealing ring arranged at the grooving position of the flange surface. In this way, through the design and the use of the pressure vessel air extraction top cover 6, especially the design of no bolt, relying on dead weight and rubber sealing rubber strip for can rely on the pressure vessel air extraction top cover 6's dead weight to realize the sealing connection of pressure vessel air extraction top cover 6 and pressure vessel, this operation is very simple, has very big help to solving major line time limit of a project of overhaul and reduction overhaul personnel collective dose rate.
In at least one embodiment of the present application, the pressure vessel extraction top cover 6 is provided with a connector connected with the reactor pressure vessel 1, and the connector has anti-loosening or anti-falling performance. Thus, by taking anti-loosening or anti-disengaging measures on the connector of the pressure vessel extraction cap 6, the connector is prevented from falling into the core during use.
In at least one embodiment of the present application, the pressure vessel extraction cap 6 is an arcuate cover plate. In this way, the suitability of the pressure vessel pumping top cover 6 and the reactor pressure vessel 1 is stronger, and the tightness of the pressure vessel pumping top cover 6 after being connected with the reactor pressure vessel 1 is improved.
In at least one embodiment of the present application, the regulator bleed cover 7 is attached to the regulator manhole by bolts and metal wrap pads. Thus, the fixing of the pressure regulator air suction cover plate 7 and the pressure regulator 2 manhole is realized by utilizing the bolts, and the tightness of the pressure regulator air suction cover plate 7 after being connected with the pressure regulator 2 manhole is improved by utilizing the metal winding pad.
Fig. 3 is a schematic flow chart of a water filling method of a primary loop system of a nuclear power plant reactor according to an embodiment of the present application. As shown in fig. 3, the water filling method includes the following steps.
S10: during low water level of the nuclear power plant and prior to reactor loading, the associated valves and primary pump mechanical seals of the nuclear power plant reactor-loop system are closed.
Specifically, after the low water level maintenance of the nuclear power plant is finished, the first loop does not start to feed water before the reactor is charged. And closing a loop related boundary valve, wherein the mechanical seal of the main pump is in a natural closing state.
S20: the pressure vessel exhaust top cover in the vacuumizing device of the nuclear power plant reactor-loop system is hoisted to the reactor pressure vessel so as to be in sealing connection with the reactor pressure vessel.
Specifically, during the low water level, the pressure vessel suction top cover 6 is hoisted to the pressure vessel 1, the installation is completed, and the sealing is realized by means of self weight.
S30: and fixedly installing a pressure stabilizer air exhaust cover plate in the vacuumizing device on a pressure stabilizer manhole.
Specifically, during low water level, the pressure regulator suction cover plate 7 is mounted on the manhole of the pressure regulator 2, and fastening is completed by bolts.
S40: one end of a vacuum ejector in the vacuumizing device is connected with a compressed air system of the nuclear power plant, and the other end of the vacuum ejector is connected with an air suction cover plate of the voltage stabilizer.
Specifically, the vacuum ejector 5 is hoisted into the nuclear island, the fixation is completed, the inlet at one end is connected with the compressed air system, and the inlet valve is closed. The other end is connected to the air extraction cover plate 7 of the voltage stabilizer through a metal hose.
It should be noted that steps S10 to S40 may be collectively referred to as a preparation operation before the primary circuit is evacuated, that is, the vacuum top cover of the pressure vessel is in place, the pressure regulator suction cover 7 is installed on the manhole of the pressure regulator 2 and connected to the vacuum ejector 5 through a hose, the air source pipeline is connected, the primary circuit is filled with water to the half pipe water level of the primary pipeline, and the other online operation of the primary circuit is completed.
S50: filling water to the upper edge of the main pipeline which is over the loop.
S60: and opening a compressed air inlet valve of the compressed air system to vacuumize so as to vacuumize a loop pressure to a preset vacuum pressure.
The preset vacuum pressure can be designed according to actual requirements, and the specific value of the preset vacuum pressure is not limited in the embodiment of the application as long as the preset vacuum pressure is lower than atmospheric pressure. For example, in some embodiments, the preset vacuum pressure is 0.17bar. For example, in other embodiments, the preset vacuum pressure is less than 0bar, i.e., the primary circuit is placed in a negative pressure state.
For example, the air supply line inlet valve and the compressed air inlet valve of the compressed air system may be opened to perform a vacuum operation, and the air in a circuit is drawn out by observing the system vacuum pressure gauge, focusing on a circuit pressure drop trend until a circuit pressure drops to 0.17bar.
S70: the water is filled into the main system by opening a loop water inlet valve, and a manual valve at the air exhaust top cover of the pressure vessel is opened to break vacuum so as to press the water in the pressure vessel of the reactor into the inverted U-shaped pipe of the steam generator.
Specifically, water is filled to the upper edge of the main pipeline of the loop (the water level is not allowed to be lower than the upper edge of the main pipeline of the loop when the vacuum is broken later, otherwise, the vacuumizing is failed), then a manual valve (also called a vacuum breaking valve) on the top cover of the pressure container is opened while water is filled to start breaking the vacuum, and the water in the pressure container is continuously pressed into a reverse U-shaped pipe of a Steam Generator (SG) by air pressure, so that the purpose of reducing the air content of the loop is realized. The breaking of the vacuum is completed until the circuit reaches atmospheric pressure. The subsequent air-content test can be qualified at one time after the operation according to the method according to Fuqing nuclear power practice, and the air-content is superior to the air-content after the main pump is used for the point-driven exhaust.
Restoration work can be carried out after the vacuum is destroyed, specifically, the top cover of the pressure vessel is lifted out, the manhole vacuumizing cover plate of the pressure stabilizer 2 is removed, the connecting hose is removed, and the vacuumizing device is lifted out.
The water filling method is a corresponding use method of the vacuumizing device of the primary loop system of the nuclear power plant reactor in the above embodiment, and related technical features and beneficial effects thereof may be referred to the description in the above embodiment, and will not be repeated here.
It should be noted that, the combination of the technical features in the embodiments of the present application is not limited to the combination described in the embodiments of the present application or the combination described in the specific embodiments, and all the technical features described in the present application may be freely combined or combined in any manner unless contradiction occurs between them.
The foregoing description of the preferred embodiments of the present invention is not intended to limit the invention to the precise form disclosed, and any modifications, equivalents, and alternatives falling within the spirit and principles of the present invention are intended to be included within the scope of the present invention.
Claims (7)
1. The utility model provides a evacuating device of nuclear power plant's reactor return circuit system, its characterized in that, nuclear power plant's reactor return circuit system includes reactor pressure vessel, stabiliser, steam generator and main pump that connect gradually, wherein, evacuating device includes:
a vacuum ejector, one end of which is connected with a compressed air system of the nuclear power plant and is configured to extract air in a loop;
the pressure vessel exhaust top cover is in sealing connection with the reactor pressure vessel, and the top is provided with a pipeline and a manual valve for breaking vacuum;
and one end of the air extraction cover plate of the voltage stabilizer is connected with the other end of the vacuum ejector, and the other end of the air extraction cover plate of the voltage stabilizer is connected with the manhole of the voltage stabilizer.
2. The vacuum extractor of claim 1 wherein the vacuum extractor comprises a vacuum pump,
the pressure vessel air exhaust top cover is contacted with the sealing surface of the pressure vessel cylinder body through a rubber sealing ring arranged at the grooving position of the flange surface.
3. The vacuum extractor of claim 1 wherein the vacuum extractor comprises a vacuum pump,
the pressure vessel air extraction top cover is an arc-shaped cover plate.
4. The vacuum extractor of claim 1 wherein the vacuum extractor comprises a vacuum pump,
the pressure vessel pumping top cover is provided with a connecting piece connected with the reactor pressure vessel, and the connecting piece has anti-loosening or anti-falling performance.
5. The vacuum pumping apparatus as claimed in any one of claims 1 to 4, wherein,
and the pressure stabilizer air exhaust cover plate is connected with the pressure stabilizer manhole through bolts and metal winding pads.
6. A method of filling water in a nuclear power plant reactor-loop system, comprising:
closing associated valves and primary pump mechanical seals of a nuclear power plant reactor-loop system during a low water level of the nuclear power plant and prior to reactor loading;
hoisting a pressure vessel extraction header in an evacuating device of a nuclear power plant reactor-loop system according to any one of claims 1 to 5 onto a reactor pressure vessel to sealingly connect the pressure vessel extraction header to the reactor pressure vessel;
fixedly mounting a pressure stabilizer air exhaust cover plate in the vacuumizing device on a pressure stabilizer manhole;
one end of a vacuum ejector in the vacuumizing device is connected with a compressed air system of the nuclear power plant, and the other end of the vacuum ejector is connected with an air suction cover plate of the voltage stabilizer;
filling water to the upper edge of the main pipeline which is over the loop;
opening a compressed air inlet valve of the compressed air system to vacuumize so as to vacuumize a loop pressure to a preset vacuum pressure;
and opening a manual valve at the air exhaust top cover of the pressure vessel to break vacuum while opening a loop water inlet valve to fill water into the main system so as to press water in the pressure vessel of the reactor into the inverted U-shaped pipe of the steam generator.
7. A water filling method according to claim 6, wherein,
the preset vacuum pressure is 0.17bar.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311750508.9A CN117703843A (en) | 2023-12-18 | 2023-12-18 | Vacuumizing device of primary loop system of nuclear power plant reactor and water filling method thereof |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311750508.9A CN117703843A (en) | 2023-12-18 | 2023-12-18 | Vacuumizing device of primary loop system of nuclear power plant reactor and water filling method thereof |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN117703843A true CN117703843A (en) | 2024-03-15 |
Family
ID=90162053
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202311750508.9A Pending CN117703843A (en) | 2023-12-18 | 2023-12-18 | Vacuumizing device of primary loop system of nuclear power plant reactor and water filling method thereof |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN117703843A (en) |
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2023
- 2023-12-18 CN CN202311750508.9A patent/CN117703843A/en active Pending
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