CN117723210A - Test system for detecting hydrogen leakage condition of steam turbine generator of nuclear power plant - Google Patents
Test system for detecting hydrogen leakage condition of steam turbine generator of nuclear power plant Download PDFInfo
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- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 title claims abstract description 60
- 229910052739 hydrogen Inorganic materials 0.000 title claims abstract description 60
- 239000001257 hydrogen Substances 0.000 title claims abstract description 60
- 238000002474 experimental method Methods 0.000 claims abstract description 60
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- 239000003086 colorant Substances 0.000 claims description 6
- 238000005259 measurement Methods 0.000 claims description 6
- 238000001514 detection method Methods 0.000 description 4
- 238000012544 monitoring process Methods 0.000 description 4
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- 230000009286 beneficial effect Effects 0.000 description 1
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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
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- 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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Abstract
The invention relates to a test system for detecting hydrogen leakage condition of a turbogenerator in a nuclear power plant. The system comprises a control module, a parameter acquisition module and a display module, wherein the display module comprises a parameter setting area, a data acquisition area, a test start-stop operation area and a leakage result display area, the parameter setting area is used for receiving a set value of a sampling flow value, the data acquisition area is used for receiving an equipment parameter list required to be acquired in a hydrogen leakage test of a steam turbine generator of a nuclear power plant, the test start-stop operation area is used for controlling the start and stop of the test, and the leakage result display area is used for displaying the test result. According to the invention, experimental parameters and experimental results can be automatically recorded and automatically calculated in the hydrogen leakage experimental process, so that the automation level of the hydrogen leakage experiment is greatly improved, and the human error risk is reduced.
Description
Technical Field
The invention relates to the field of detection of turbogenerators in nuclear power plants, in particular to a test system for detecting hydrogen leakage conditions of a turbogenerator in a nuclear power plant.
Background
The nuclear power is taken as a green safe energy source and is an important component of energy supply. Ensuring the safety of a nuclear power plant firstly ensures the safe operation of various devices of the nuclear power plant, so that the devices need to be detected safely at regular intervals. The steam turbine generator of the nuclear power plant is used as large-scale power generation equipment, is important equipment of the nuclear power plant, and needs to be subjected to safety detection regularly.
The test for detecting the hydrogen leakage condition of the turbogenerator of the nuclear power plant, namely the T-xGRV 001 test, is an important detection content when the turbogenerator of the nuclear power plant is safely detected. In the prior art, when the hydrogen leakage of the turbonator is detected, parameter recording and calculation are completely carried out manually, and because the detection time is long (24 hours are usually required) and the data size is large, the risk of human error is easy to occur, and certain potential safety hazard exists.
Disclosure of Invention
The invention aims to solve the technical problem of providing a test system for detecting the hydrogen leakage condition of a steam turbine generator of a nuclear power plant.
The technical scheme adopted for solving the technical problems is as follows: the test system for detecting the hydrogen leakage condition of the steam turbine generator of the nuclear power plant is constructed and comprises a control module, a parameter acquisition module and a display module, wherein the control module is respectively connected with the parameter acquisition module and the display module;
the display module comprises a parameter setting area, a data acquisition area, a test start-stop operation area and a leakage result display area, wherein the parameter setting area is used for receiving a set value of a sampling flow value, the data acquisition area is used for receiving a device parameter list required to be acquired in a hydrogen leakage test of a steam turbine generator of a nuclear power plant, the test start-stop operation area is used for controlling the start and stop of the test, and the leakage result display area is used for displaying the test result;
after the experiment starting and stopping operation area receives an experiment starting instruction, the control module controls the parameter acquisition module to acquire the parameter information of each device in the device parameter list; and after the test start-stop operation area receives the test stop instruction, the control module processes the equipment parameter information by using a preset algorithm to obtain an experiment result, and the experiment result is displayed in the leakage result display area.
Further, in the test system for detecting the hydrogen leakage condition of the steam turbine generator in the nuclear power plant, the display module displays preset reminding information after the test start-stop operation area receives the test start instruction and before the test start-stop operation area receives the test stop instruction, and the preset reminding information is used for reminding a worker that the experiment is currently in progress.
Furthermore, in the test system for detecting the hydrogen leakage condition of the steam turbine generator of the nuclear power plant, the test start-stop operation area is also used for displaying the test start time and the test stop time.
Further, in the test system for detecting the hydrogen leakage condition of the steam turbine generator of the nuclear power plant, the test start-stop operation area comprises a virtual start button for generating an experiment start instruction and a virtual stop button for generating an experiment stop instruction.
Further, in the test system for detecting hydrogen leakage of a turbogenerator in a nuclear power plant according to the present invention, the parameter setting area includes an input box for receiving a set value of the sampled flow value.
Further, in the test system for detecting hydrogen leakage of a turbogenerator in a nuclear power plant according to the present invention, the parameter setting area displays a preset flow list including at least two preset flow values, and the preset flow in the preset flow list is selected as a set value according to a selection instruction.
Further, in the test system for detecting the hydrogen leakage condition of the turbogenerator in the nuclear power plant, the display module displays the start-stop operation area of the test by using colors; or alternatively
The display module uses different colors to display the parameter setting area, the data acquisition area, the test start-stop operation area and the leakage result display area in a distinguishing mode.
Further, in the test system for detecting the hydrogen leakage condition of the steam turbine generator of the nuclear power plant, the equipment parameter information comprises equipment pressure and equipment temperature.
Further, in the test system for detecting hydrogen leakage of a turbogenerator in a nuclear power plant according to the present invention, the test results include a fixed leakage rate for measurement, a total leakage rate, and a final leakage rate;
the preset algorithm includes a first algorithm for calculating a fixed leak rate for the measurement, a second algorithm for calculating a total leak rate, and a third algorithm for calculating a final leak rate.
Further, in the test system for detecting the hydrogen leakage condition of the steam turbine generator in the nuclear power plant, the control module compares the final leakage rate with a preset standard leakage rate to obtain an experimental result.
The test system for detecting the hydrogen leakage condition of the steam turbine generator of the nuclear power plant has the following beneficial effects: according to the invention, experimental parameters and experimental results can be automatically recorded and automatically calculated in the hydrogen leakage experimental process, so that the automation level of the hydrogen leakage experiment is greatly improved, and the human error risk is reduced.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a schematic diagram of a test system for detecting hydrogen leakage of a turbogenerator in a nuclear power plant according to an embodiment of the present invention;
FIG. 2 is a software screenshot of a display module in a test system for detecting hydrogen leakage of a turbogenerator in a nuclear power plant according to an embodiment of the present invention;
fig. 3 is a software screenshot of a monitoring system for a steam turbine generator in a nuclear power plant according to an embodiment of the present invention.
Detailed Description
For a clearer understanding of technical features, objects and effects of the present invention, a detailed description of embodiments of the present invention will be made with reference to the accompanying drawings.
In a preferred embodiment, referring to fig. 1, the test system for detecting hydrogen leakage of a turbo generator in a nuclear power plant according to this embodiment includes a control module, a parameter acquisition module, and a display module, where the control module is connected to the parameter acquisition module and the display module, respectively, and the control module, the parameter acquisition module, and the display module are described below.
The display module comprises a parameter setting area, a data acquisition area, a test start-stop operation area and a leakage result display area, wherein the parameter setting area, the data acquisition area, the test start-stop operation area and the leakage result display area are distributed in the same interface of the display module, but the display position, the area size and the display sequence of the parameter setting area, the data acquisition area, the test start-stop operation area and the leakage result display area are not limited, and the display position, the area size and the display sequence of the parameter setting area, the data acquisition area, the test start-stop operation area and the leakage result display area in the display module can be flexibly set according to requirements. Alternatively, the display module is a display, projector, or video wall, etc. Referring to fig. 2, a screenshot of a display module in an actual software product in an embodiment is shown, where the area ranges of a parameter setting area, a data acquisition area, a test start-stop operation area and a leakage result display area are respectively given.
The parameter setting area is used for receiving the set value of the sampling flow value, namely, the set value of the sampling flow value required by the experiment is selected or input in the parameter setting area by a worker. The specific value of the set value is set according to the experimental requirement, which is not limited in this embodiment. For example, the sample flow rates of GRV0121LD and GRV0122LD are 500mL/min.
The data acquisition area is used for receiving an equipment parameter list required to be acquired in a hydrogen leakage test of a steam turbine generator of the nuclear power plant, wherein the equipment parameter list comprises equipment names or models required to be acquired and parameter information of the equipment, such as temperature, pressure and the like, and the acquired equipment parameter information is recorded in real time. It can be understood that, since the device parameter list required by the hydrogen leakage test of the steam turbine generator of the nuclear power plant is already available in the prior art, the staff only needs to input the device parameter list in the data acquisition area according to the requirement of the existing scheme, and the specific content of the device parameter list can refer to the prior art. It will be appreciated that the device parameter information needs to be continuously collected and recorded throughout the experimental period from the start of the experiment to the stop of the experiment.
When the equipment parameter information is acquired, the equipment parameter information can be directly acquired from corresponding equipment, can be directly read from an existing interface of a Digital Control System (DCS) of the nuclear power plant, and can be selected according to requirements.
The test start-stop operating area is used for controlling the start and stop of the test. When the test of the hydrogen leakage condition of the turbogenerator of the nuclear power plant needs to be started, a worker applies operation in the test start-stop operation area, so that the test start-stop operation area generates an experiment start instruction. The test start-stop operation area transmits an experiment start-up instruction to the control module, and the control module starts the system to start data acquisition after receiving the experiment start-up instruction. After the experiment is finished, when the experiment of the hydrogen leakage condition of the turbogenerator of the nuclear power plant needs to be stopped, a worker applies operation in the experiment start-stop operation area, so that the experiment start-stop operation area generates an experiment stop instruction. The test start-stop operation area transmits an experiment stop instruction to the control module, and the control module stops data acquisition after receiving the experiment stop instruction and enters an acquisition data processing stage.
The leakage result display area is used for displaying experimental results. The control module stores a preset algorithm for processing the equipment parameter information acquired in the experimental process, and after the experiment is stopped, the control module processes the equipment parameter information by using the preset algorithm to obtain an experimental result, and the experimental result is displayed in a leakage result display area for workers to check. Or, a memory connected with the control module is stored with a preset algorithm for processing the equipment parameter information acquired in the experimental process, the control module reads the preset algorithm stored in the memory, and after the experiment is stopped, the control module processes the equipment parameter information by using the preset algorithm to obtain an experimental result, and the experimental result is displayed in a leakage result display area for the staff to check.
The working principle of the test system for detecting the hydrogen leakage condition of the turbogenerator in the nuclear power plant in this embodiment is as follows:
when the test of the hydrogen leakage condition of the turbonator is required, a worker applies operation in a test start-stop operation area to generate an experiment start instruction. After receiving the experiment starting instruction, the control module controls the parameter acquisition module to acquire the information of each device parameter in the device parameter list. When the test of the hydrogen leakage condition of the turbogenerator of the nuclear power plant needs to be stopped after the test is finished, a worker applies operation in a test start-stop operation area to generate an experiment stop instruction. And after receiving the experiment stopping instruction, the control module stops collecting the equipment parameters and reads a preset algorithm. The control module processes the equipment parameter information by using a preset algorithm to obtain an experimental result, and the experimental result is displayed in a leakage result display area.
Alternatively, the test system for detecting the hydrogen leakage condition of the steam turbine generator of the nuclear power plant in this embodiment may be implemented by a Digital Control System (DCS) of the nuclear power plant.
Compared with the prior art, the method and the device can automatically record experimental parameters and automatically calculate experimental results in the hydrogen leakage experimental process, and completely rely on manpower to record and calculate data, so that the automation level of the hydrogen leakage experiment is greatly improved, the risk of human error is reduced, and meanwhile, the labor intensity of staff is reduced.
In some embodiments of the test system for detecting hydrogen leakage from a turbogenerator in a nuclear power plant, the test is typically performed for a long period of time, typically 24 hours, and is not interrupted. In order to prevent misoperation of other staff, the display module of the embodiment displays preset reminding information after the experiment start-stop operation area receives the experiment start instruction and before the experiment start-stop operation area receives the experiment stop instruction, and the preset reminding information is used for reminding the staff that the experiment is currently in progress. Alternatively, to make the preset reminder information more noticeable, the preset reminder information may be displayed using a background color, such as a red background color. For example, the preset reminding information is "please note: the T3GR001 test "is being performed, and the red background color display" please note: the T3GR001 test is being performed. In addition, referring to fig. 3, a software screenshot of the monitoring system of the turbo generator in the nuclear power plant is taken, and in order to prevent misoperation of the staff during the experiment, the preset reminding information is displayed in the monitoring system of the turbo generator in the nuclear power plant, so as to prompt the staff that the experiment is in progress. The monitoring system of the turbogenerator in the nuclear power plant in fig. 3 can refer to the prior art, and this embodiment will not be described in detail.
In some embodiments of the test system for detecting hydrogen leakage of a turbogenerator in a nuclear power plant, in order to facilitate a worker to record the test time, the test start-stop operation area of the embodiment is further used for displaying the test start time and the test stop time. When the experiment starts, namely when the control module receives an experiment starting instruction, the control module reads the current time of the timer and displays the current time in the experiment starting and stopping operation area as the experiment starting time. When the experiment is stopped, namely when the control module receives an experiment stopping instruction, the control module reads the current time of the timer and displays the current time in the experiment starting and stopping operation area as the experiment stopping time. Alternatively, the test start-stop operation area may also display the test accumulated time in real time. Compared with the prior art, the embodiment can automatically record the time such as the starting time and the ending time of the experiment by means of manual recording time, and can reduce the labor intensity of workers.
In some embodiments of the test system for detecting hydrogen leakage of a turbogenerator in a nuclear power plant, referring to fig. 2, the test start-stop operation area includes a virtual start button for generating a test start command and a virtual stop button for generating a test stop command. In fig. 2, the T1 SET virtual button is a virtual start button, and the T2 SET virtual button is a virtual stop button. Further, when the test of the hydrogen leakage condition of the turbogenerator of the nuclear power plant needs to be started, a worker applies operation to the virtual start button, for example, a click operation is applied through a mouse or a touch screen, so that the virtual start button generates an experiment start instruction. When the test of the hydrogen leakage condition of the turbogenerator of the nuclear power plant needs to be stopped, a worker applies a clicking operation on the virtual stop button, for example, by using a mouse or a touch screen, so that the virtual stop button generates an experiment stop instruction. Alternatively, the experiment starting time obtained in the above embodiment is correspondingly displayed beside the virtual starting button in the present embodiment, and the experiment stopping time obtained in the above embodiment is correspondingly displayed beside the virtual stopping button in the present embodiment, so as to facilitate the staff to observe the experiment time. In the embodiment, by setting the virtual start button and the virtual stop button, the start and stop of the experiment can be controlled by a worker conveniently.
In some embodiments of the test system for detecting a hydrogen leakage condition of a turbogenerator in a nuclear power plant, the parameter setting area is configured to receive a set value of a sampled flow value, and for convenience of a worker to flexibly input any required data, the parameter setting area in this embodiment includes an input box configured to receive the set value of the sampled flow value, the worker inputs the required set value in the input box through an input device such as a keyboard, and the input box transmits the received set value to the control module.
In some embodiments of the test system for detecting a hydrogen leakage condition of a turbogenerator in a nuclear power plant, the parameter setting area is configured to receive a set value of a sampled flow value, and the common values can be enumerated in consideration of limited values in the test process, so that the parameter setting area in this embodiment displays a preset flow list including at least two preset flow values, and selects a preset flow in the preset flow list as a set value according to a selection instruction, that is, a worker selects one of the preset flow values in the preset flow list as the set value, and transmits the selected set value to the control module.
In some embodiments of the test system for detecting hydrogen leakage of a turbogenerator in a nuclear power plant, in consideration of the fact that the test cannot be stopped in the middle of the test, in order to prevent a worker from touching the test start-stop operation area by mistake, the test start-stop operation area can be displayed in the display module by using colors so as to start a reminding function.
In some embodiments of the test system for detecting a hydrogen leakage condition of a turbogenerator in a nuclear power plant, in order to facilitate a worker to distinguish different working areas in a display module, the display module of the embodiment uses different colors to distinguish a display parameter setting area, a data acquisition area, a test start-stop operation area and a leakage result display area, so that the worker can quickly distinguish and define a certain working area through the colors.
In some embodiments of the test system for detecting hydrogen leakage from a nuclear power plant turbo generator, the plant parameter information includes plant pressure and plant temperature. Referring to FIG. 2, the device pressure and device temperature for some of the site information is shown. The device names in the figure use the device model numbers. The equipment of different nuclear power plants is different, and the technical personnel can flexibly adjust the equipment according to actual needs.
In some embodiments of the test system for detecting hydrogen leakage of a turbogenerator in a nuclear power plant, the test results include a fixed leakage rate for measurement, a total leakage rate, and a final leakage rate, and the preset algorithm includes a first algorithm for calculating the fixed leakage rate for measurement, a second algorithm for calculating the total leakage rate, and a third algorithm for calculating the final leakage rate. It can be understood that the first algorithm corresponding to the fixed leakage rate, the second algorithm corresponding to the total leakage rate, and the third algorithm corresponding to the final leakage rate may refer to the prior art, and this embodiment will not be described again.
In some embodiments of the test system for detecting hydrogen leakage of a turbogenerator in a nuclear power plant, after the final leakage rate is obtained through the above embodiments, the control module reads a preset standard leakage rate, where the preset standard leakage rate is a standard leakage rate required by an experiment acceptance criterion and an experiment. And the control module compares the final leakage rate with a preset standard leakage rate to obtain an experimental result, and the experimental result is displayed in a leakage result display area. By comparison, if the final leak rate is greater than the predetermined standard leak rate, it is indicated that the leak rate is unsatisfactory, a safety check is required, and measures are taken to reduce the leak rate. And if the final leakage rate is not greater than the preset standard leakage rate, indicating that the leakage rate meets the requirement, and ending the integral tightness test of the steam turbine generator.
In the present specification, each embodiment is described in a progressive manner, and each embodiment is mainly described in a different point from other embodiments, and identical and similar parts between the embodiments are all enough to refer to each other. For the device disclosed in the embodiment, since it corresponds to the method disclosed in the embodiment, the description is relatively simple, and the relevant points refer to the description of the method section.
Those of skill would further appreciate that the various illustrative elements and algorithm steps described in connection with the embodiments disclosed herein may be implemented as electronic hardware, computer software, or combinations of both, and that the various illustrative elements and steps are described above generally in terms of functionality in order to clearly illustrate the interchangeability of hardware and software. Whether such functionality is implemented as hardware or software depends upon the particular application and design constraints imposed on the solution. Skilled artisans may implement the described functionality in varying ways for each particular application, but such implementation decisions should not be interpreted as causing a departure from the scope of the present invention.
The steps of a method or algorithm described in connection with the embodiments disclosed herein may be embodied directly in hardware, in a software module executed by a processor, or in a combination of the two. The software modules may be disposed in Random Access Memory (RAM), memory, read Only Memory (ROM), electrically programmable ROM, electrically erasable programmable ROM, registers, hard disk, a removable disk, a CD-ROM, or any other form of storage medium known in the art.
The above embodiments are provided to illustrate the technical concept and features of the present invention and are intended to enable those skilled in the art to understand the content of the present invention and implement the same according to the content of the present invention, and not to limit the scope of the present invention. All equivalent changes and modifications made with the scope of the claims should be covered by the claims.
Claims (10)
1. The test system for detecting the hydrogen leakage condition of the steam turbine generator of the nuclear power plant is characterized by comprising a control module, a parameter acquisition module and a display module, wherein the control module is respectively connected with the parameter acquisition module and the display module;
the display module comprises a parameter setting area, a data acquisition area, a test start-stop operation area and a leakage result display area, wherein the parameter setting area is used for receiving a set value of a sampling flow value, the data acquisition area is used for receiving a device parameter list required to be acquired in a hydrogen leakage test of a steam turbine generator of a nuclear power plant, the test start-stop operation area is used for controlling the start and stop of the test, and the leakage result display area is used for displaying the test result;
after the experiment starting and stopping operation area receives an experiment starting instruction, the control module controls the parameter acquisition module to acquire the parameter information of each device in the device parameter list; and after the test start-stop operation area receives the test stop instruction, the control module processes the equipment parameter information by using a preset algorithm to obtain an experiment result, and the experiment result is displayed in the leakage result display area.
2. The test system for detecting a hydrogen leakage condition of a steam turbine generator in a nuclear power plant according to claim 1, wherein the display module displays preset reminding information after the test start-stop operation area receives the test start instruction and before the test start-stop operation area receives the test stop instruction, and the preset reminding information is used for reminding a worker that an experiment is currently in progress.
3. The test system for detecting a hydrogen leakage condition of a steam turbine generator of a nuclear power plant according to claim 1, wherein the test start-stop operation area is further used for displaying a test start time and a test stop time.
4. The test system for detecting a hydrogen leakage condition of a steam turbine generator of a nuclear power plant according to claim 1, wherein the test start-stop operation area includes a virtual start button for generating an experiment start instruction and a virtual stop button for generating an experiment stop instruction.
5. The test system for detecting a hydrogen leak in a steam turbine generator of a nuclear power plant according to claim 1, wherein the parameter setting area includes an input box for receiving a set value of the sampled flow value.
6. The test system for detecting a hydrogen leakage condition of a steam turbine generator of a nuclear power plant according to claim 1, wherein the parameter setting area displays a preset flow list including at least two preset flow values, and the preset flow in the preset flow list is selected as a set value according to a selection instruction.
7. The test system for detecting a hydrogen leakage condition of a steam turbine generator of a nuclear power plant according to claim 1, wherein the display module displays the test start-stop operation region using a color; or alternatively
The display module uses different colors to display the parameter setting area, the data acquisition area, the test start-stop operation area and the leakage result display area in a distinguishing mode.
8. The test system for detecting hydrogen leakage from a steam turbine generator of a nuclear power plant of claim 1, wherein the plant parameter information includes plant pressure and plant temperature.
9. The test system for detecting hydrogen leakage of a steam turbine generator of a nuclear power plant according to claim 1, wherein the test results include a fixed leakage rate for measurement, a total leakage rate, and a final leakage rate;
the preset algorithm includes a first algorithm for calculating a fixed leak rate for the measurement, a second algorithm for calculating a total leak rate, and a third algorithm for calculating a final leak rate.
10. The test system for detecting a hydrogen leakage condition of a steam turbine generator of a nuclear power plant according to claim 9, wherein the control module compares the final leakage rate with a preset standard leakage rate to obtain an experimental result.
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