CN112489840A - Tracer injection equipment for steam humidity measurement test of nuclear power plant - Google Patents
Tracer injection equipment for steam humidity measurement test of nuclear power plant Download PDFInfo
- Publication number
- CN112489840A CN112489840A CN202011261914.5A CN202011261914A CN112489840A CN 112489840 A CN112489840 A CN 112489840A CN 202011261914 A CN202011261914 A CN 202011261914A CN 112489840 A CN112489840 A CN 112489840A
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- China
- Prior art keywords
- power plant
- nuclear power
- tracer
- measurement test
- humidity measurement
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- 238000002347 injection Methods 0.000 title claims abstract description 74
- 239000007924 injection Substances 0.000 title claims abstract description 74
- 239000000700 radioactive tracer Substances 0.000 title claims abstract description 57
- 238000005259 measurement Methods 0.000 title claims abstract description 40
- 238000002955 isolation Methods 0.000 claims description 12
- 239000007788 liquid Substances 0.000 claims description 10
- 229910001220 stainless steel Inorganic materials 0.000 claims description 3
- 239000010935 stainless steel Substances 0.000 claims description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 20
- 238000000034 method Methods 0.000 abstract description 8
- 230000008569 process Effects 0.000 abstract description 7
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 abstract description 6
- 229910052760 oxygen Inorganic materials 0.000 abstract description 6
- 239000001301 oxygen Substances 0.000 abstract description 6
- 230000003628 erosive effect Effects 0.000 abstract description 4
- 230000006872 improvement Effects 0.000 description 9
- 239000003795 chemical substances by application Substances 0.000 description 4
- 239000000243 solution Substances 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 230000015572 biosynthetic process Effects 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000005070 sampling Methods 0.000 description 2
- 238000003756 stirring Methods 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 238000007865 diluting Methods 0.000 description 1
- 239000000428 dust Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000002265 prevention Effects 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 239000010865 sewage Substances 0.000 description 1
- 230000007704 transition Effects 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/006—Details of nuclear power plant primary side of steam generators
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
-
- 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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses tracer injection equipment for a steam humidity measurement test of a nuclear power plant, which comprises: the bottom of the container is provided with an opening, and the opening is connected with an injection pipe; and the vortex preventing device is arranged at the bottom of the container and positioned above the opening, and comprises a vortex preventing disc and guide plates distributed in a fan shape, wherein the guide plates are uniformly distributed around the opening. Compared with the prior art, the tracer injection equipment for the steam humidity measurement test of the nuclear power plant prevents the tracer from forming vortex in the injection process, on one hand, the influence on the dissolved oxygen amount of condensed water is avoided, and on the other hand, the risk of cavitation erosion of the condensed water pump caused by the introduced air is eliminated. In addition, the tracer injection equipment for the steam humidity measurement test of the nuclear power plant allows injection at a larger flow rate, and improves the tracer injection efficiency.
Description
Technical Field
The invention belongs to the technical field of nuclear power, and particularly relates to tracer injection equipment for a steam humidity measurement test of a nuclear power plant.
Background
At present, nuclear power plants generally include a reactor, a one-circuit system, and a two-circuit system. Nuclear fission occurs in a reactor core composed of nuclear fuel, and the heat given off by the nuclear fission is carried out of the reactor by high pressure water flowing through a primary loop system of the reactor core and transferred to water in a secondary loop in a steamer generator. The steam generated by the heated water in the two loops pushes the steam turbine to rotate, so as to drive the generator to generate electricity.
The steam generator humidity measurement test is a key unit performance assessment test, and the test result directly reflects the steam quality at the outlet of the steam generator. The test principle is as follows: introducing a non-radioactive tracer, and detecting and calculating the steam humidity at the outlet of the steam generator by using the tracer. After the tracer injection operation during the steam generator humidity measurement test is completed, a representative sample needs to be obtained at sampling points such as a steam-water separation reheater, a condenser, steam generator feed water, steam generator blowdown, a steam-water interface of an upper section of the steam generator and the like, and the concentration of tracer elements in the representative sample is detected so as to be used for tracer balance judgment and calculation of the humidity inside the steam generator.
The injection of the tracer agent is the premise of sample concentration detection and steam humidity calculation, and the tracer agent is conveniently and quickly injected into the secondary loop water circulation of the nuclear power plant under the condition of not influencing the safe operation of a unit, so that the smooth implementation of the humidity measurement test of the nuclear power plant is ensured. The injection of the tracer requires that a suction inlet is in negative pressure, so that air is easy to leak, thereby influencing the operation of a condensed water pump, even causing cavitation erosion, and influencing an oxygen-containing device of the condensed water.
At present, the injection method of the tracer agent during the humidity measurement test of the steam generator of the nuclear power plant is as follows: before the test, connecting the injection equipment to a sewage (sampling) discharge pipe of an inlet main pipe of the condensate pump to be injected; preparing a solution (1L) by using a tracer agent with specified mass in advance in a laboratory; when injecting, pouring the tracer solution into injection equipment, and diluting with 80L of demineralized water; and opening a drain valve of a condensate pump inlet main pipe and an injection equipment isolation valve in sequence, starting injection, observing the liquid level during injection, closing the injection equipment isolation valve to 1/3 degrees when the distance between the liquid level and the bottom of the container is less than 100mm, and slowing down the injection speed. When the liquid level is less than 50mm from the bottom of the container, the injection device isolation valve is closed, and injection is finished to prevent air from being sucked. During the injection, attention should be paid to the liquid level of the suction inlet at any time, and whether or not a vortex is formed.
The condensate pump inlet main pipe is communicated with a turbine condenser and is a negative pressure pipeline, air is easily sucked when tracer solution is sucked, the dissolved oxygen of condensate water is increased, and the normal operation of the condensate pump is influenced, so that pipelines and joints of injection equipment are required to be well sealed. However, the air suction caused by the vortex formed on the liquid surface is often larger than the air amount leaked from the seal, and the air suction is more frequent, which is a difficulty in the injection process. According to the conventional unit test statistics, if no interference is performed, a vortex is formed when the liquid level is 200-250 mm away from the bottom of the container. Even if the formation of the vortex is disturbed by appropriate stirring, the vortex will appear at a slightly lower level and the stirring itself will generate bubbles in the water, which will also be sucked into the condensate header. Therefore, the prior art cannot fundamentally solve the air inhalation problem caused by the swirl.
In view of the above, it is necessary to provide a tracer injection device for a steam humidity measurement test in a nuclear power plant, so as to solve the problem of vortex in the tracer injection process.
Disclosure of Invention
The invention aims to: the defect of the prior art is overcome, a tracer injection device for a steam humidity measurement test of a nuclear power plant is provided, the vortex problem in the tracer injection process is solved, and the risk of oxygen content increase of condensed water or cavitation corrosion of a condensed water pump caused by air suction in the injection process is avoided.
In order to achieve the above object, the present invention provides a tracer injection apparatus for a steam humidity measurement test in a nuclear power plant, including:
the bottom of the container is provided with an opening, and the opening is connected with an injection pipe; and
and the vortex preventing device is arranged at the bottom of the container and is positioned above the opening.
As an improvement of the tracer injection equipment for the steam humidity measurement test of the nuclear power plant, the anti-vortex device comprises an anti-vortex disc and guide plates which are distributed in a fan shape, and the guide plates are uniformly distributed around the opening.
As an improvement of the tracer injection equipment for the steam humidity measurement test of the nuclear power plant, the upper edge and the lower edge of the guide plate are respectively welded and connected with the vortex prevention disc and the bottom of the container.
As an improvement of the tracer injection equipment for the steam humidity measurement test of the nuclear power plant, the anti-vortex device comprises guide plates which prevent vortex plates 8 and fans from being uniformly distributed around the opening.
As an improvement of the tracer injection equipment for the steam humidity measurement test of the nuclear power plant, the tracer injection equipment is characterized in that a lifting lug is arranged on the outer side wall of the container.
As an improvement of the tracer injection equipment for the steam humidity measurement test of the nuclear power plant, the outer side wall of the container is uniformly provided with 3 lifting lugs along the periphery of the container.
As an improvement of tracer injection equipment for a steam humidity measurement test of a nuclear power plant, the injection pipe is connected with an isolation valve, and the isolation valve is connected with a drain pipe of a condensate pump inlet main pipe through a hose.
As an improvement of the tracer injection equipment for the steam humidity measurement test of the nuclear power plant, the hose is connected with a drain pipe of a condensate pump inlet main pipe through a quick connector.
As an improvement of the tracer injection equipment for the steam humidity measurement test of the nuclear power plant, the liquid level is lowered to be flush with the vortex-proof plate, the isolation valve is closed, and the injection is stopped.
As an improvement of the tracer injection equipment for the steam humidity measurement test of the nuclear power plant, the container is a semi-closed container, and a stainless steel cover is removably arranged on the semi-closed container.
Compared with the prior art, the tracer injection equipment for the steam humidity measurement test of the nuclear power plant prevents the tracer from forming vortex in the injection process, on one hand, the influence on the dissolved oxygen amount of condensed water is avoided, and on the other hand, the risk of cavitation erosion of the condensed water pump caused by the introduced air is eliminated. The tracer injection equipment for the steam humidity measurement test of the nuclear power plant allows injection at a larger flow rate, and improves the tracer injection efficiency. In addition, the adoption of the quick connector ensures the convenience that the injection equipment can be conveniently connected to a pipeline of the running pump and quickly switched to another pipeline when the connected pipeline is blocked.
Drawings
The tracer injection device for the steam humidity measurement test of the nuclear power plant of the present invention is described in detail below with reference to the accompanying drawings and the detailed description, wherein:
fig. 1 is a schematic structural diagram of a tracer injection device for a steam humidity measurement test of a nuclear power plant according to the present invention.
Fig. 2 is a schematic structural diagram of an anti-vortex device in tracer injection equipment for a steam humidity measurement test of a nuclear power plant.
Fig. 3 is a schematic structural diagram of a baffle plate in the anti-vortex device shown in fig. 2.
Detailed Description
In order to make the objects, technical solutions and technical effects of the present invention more clear, the present invention will be further described in detail with reference to the accompanying drawings and the detailed description. It should be understood that the detailed description and specific examples, while indicating the preferred embodiment of the invention, are intended for purposes of illustration only and are not intended to limit the scope of the invention.
Referring to fig. 1, the present invention provides a tracer injection apparatus for a steam humidity measurement test of a nuclear power plant, including:
a container 10 having an opening (not shown) at the bottom of the container 10, the opening being connected to an injection pipe 20; and
and the vortex preventing device 30 is arranged at the bottom of the container 10 and is positioned above the opening.
Referring to fig. 2 and 3, in the illustrated embodiment, the vortex preventing device 30 includes a vortex preventing plate 300 and a fan-shaped baffle 302, and the baffle 302 is uniformly distributed around the opening and is substantially perpendicular to the bottom wall of the vessel 10. According to an embodiment of the present invention, the vortex preventing device 30 comprises a vortex preventing plate 300 and 8 flow guiding plates 302 uniformly distributed around the opening, and the 8 flow guiding plates 302 are spaced close to the side of the opening to facilitate the inflow of liquid from the gap between the adjacent flow guiding plates 302 and prevent the occurrence of vortex. According to one embodiment of the invention, the upper and lower edges of the baffle 302 are welded to the vortex breaker 300 and the bottom of the vessel 10, respectively.
Referring to fig. 1, according to an embodiment of the present invention, the outer sidewall of the container 10 is provided with lifting lugs (not shown), for example, the outer sidewall of the container 10 is provided with 3 lifting lugs uniformly along the circumference of the container 10, so as to facilitate the equipment to be lifted into a condensate pump pit and fixed on a vehicle for transportation during a transition.
With continued reference to FIG. 1, in accordance with one embodiment of the present invention, an isolation valve 40 is connected to the fill pipe 20, and the isolation valve 40 is connected to a drain (not shown) of the condensate pump inlet header by a hose (not shown). When the test is prepared, the drain pipes of the two condensate pumps are selected optionally, female heads of the quick connectors are installed, the quick connectors are installed on the hoses, the quick connectors are directly inserted into one ends of the female heads to complete connection during injection, the sealing is good, and air cannot leak into the condensate pumps through the connectors. Can ensure that the condensate pump can be quickly connected to the pipeline where the condensate pump runs regardless of the standby running state of the condensate pump. During injection, a fully-open isolation valve can be adopted all the time, the injection is carried out at the full flow rate of the equipment, and the injection can be stopped if the liquid level is lowered to be flush with the vortex preventing disc 300.
With continued reference to fig. 1, in accordance with one embodiment of the present invention, the container 10 is a semi-enclosed container with an open top, and a stainless steel cover (not shown) is removably attached to the semi-enclosed container 10 to prevent dust or debris from falling into the container 10 when the injection site is placed in advance.
In combination with the above detailed description of the specific embodiment of the present invention, it can be seen that, compared with the prior art, the tracer injection device for the steam humidity measurement test of the nuclear power plant of the present invention prevents the formation of vortexes during the tracer injection process, on one hand, the influence on the dissolved oxygen amount of the condensed water is avoided, and on the other hand, the risk of cavitation erosion of the condensed water pump caused by the introduced air is also eliminated. The tracer injection equipment for the steam humidity measurement test of the nuclear power plant allows injection at a larger flow rate, and improves the tracer injection efficiency. In addition, the adoption of the quick connector ensures the convenience that the injection equipment can be conveniently connected to a pipeline of the running pump and quickly switched to another pipeline when the connected pipeline is blocked.
Appropriate changes and modifications to the embodiments described above will become apparent to those skilled in the art from the disclosure and teachings of the foregoing description. Therefore, the present invention is not limited to the specific embodiments disclosed and described above, and some modifications and variations of the present invention should fall within the scope of the claims of the present invention. Furthermore, although specific terms are employed herein, they are used in a generic and descriptive sense only and not for purposes of limitation.
Claims (10)
1. A tracer injection device for a steam humidity measurement test of a nuclear power plant, comprising:
the bottom of the container is provided with an opening, and the opening is connected with an injection pipe; and
and the vortex preventing device is arranged at the bottom of the container and is positioned above the opening.
2. The tracer injector apparatus for a nuclear power plant steam humidity measurement test according to claim 1, wherein the anti-vortex device includes an anti-vortex plate and a fan-shaped distribution of deflectors, the deflectors being evenly distributed around the opening.
3. The tracer injector for steam humidity measurement test of nuclear power plant according to claim 2, wherein the upper edge and the lower edge of the baffle are respectively welded with the scroll-proof plate and the bottom of the container.
4. The tracer injector apparatus for a nuclear power plant steam humidity measurement test according to claim 2, wherein the anti-vortex device includes baffles that prevent the vortex 8 fan from being evenly distributed around the opening.
5. The tracer injection apparatus for a nuclear power plant steam humidity measurement test according to claim 1, wherein an outer sidewall of the vessel is provided with a lifting lug.
6. The tracer injector for steam humidity measurement test of nuclear power plant according to claim 5, wherein the outer sidewall of the vessel is uniformly provided with 3 lifting lugs along the circumference of the vessel.
7. The tracer injection equipment for the steam humidity measurement test of the nuclear power plant according to claim 1, wherein the injection pipe is connected with an isolation valve, and the isolation valve is connected with a drain pipe of a condensate pump inlet main pipe through a hose.
8. The tracer injector for steam humidity measurement test of nuclear power plant according to claim 7, wherein the hose is connected to a drain pipe of the condensate pump inlet main pipe through a quick connector.
9. The tracer injector for nuclear power plant steam humidity measurement test according to claim 7, wherein the liquid level drops to a level flush with the vortex plate, the isolation valve is closed, and injection is stopped.
10. The tracer injection apparatus for nuclear power plant steam moisture measurement tests according to any one of claims 1 to 9, wherein the vessel is a semi-closed vessel having a stainless steel cover removably disposed thereon.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011261914.5A CN112489840A (en) | 2020-11-12 | 2020-11-12 | Tracer injection equipment for steam humidity measurement test of nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011261914.5A CN112489840A (en) | 2020-11-12 | 2020-11-12 | Tracer injection equipment for steam humidity measurement test of nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN112489840A true CN112489840A (en) | 2021-03-12 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202011261914.5A Pending CN112489840A (en) | 2020-11-12 | 2020-11-12 | Tracer injection equipment for steam humidity measurement test of nuclear power plant |
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| CN (1) | CN112489840A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114018495A (en) * | 2021-11-08 | 2022-02-08 | 西安热工研究院有限公司 | Condenser tracing online leak detection device and leak detection method |
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| US20130160878A1 (en) * | 2011-12-22 | 2013-06-27 | Mega Fluid Systems, Inc. | Vortex reduction cap |
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2020
- 2020-11-12 CN CN202011261914.5A patent/CN112489840A/en active Pending
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114018495A (en) * | 2021-11-08 | 2022-02-08 | 西安热工研究院有限公司 | Condenser tracing online leak detection device and leak detection method |
| CN114018495B (en) * | 2021-11-08 | 2023-11-14 | 西安热工研究院有限公司 | On-line leakage detection equipment and leakage detection method for tracing of condenser |
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Application publication date: 20210312 |
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