CN116480433A - Method and device for producing externally supplied industrial steam and electronic equipment - Google Patents
Method and device for producing externally supplied industrial steam and electronic equipment Download PDFInfo
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- 229920006395 saturated elastomer Polymers 0.000 claims abstract description 40
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- 230000008569 process Effects 0.000 claims abstract description 30
- 238000010438 heat treatment Methods 0.000 claims abstract description 20
- 230000005855 radiation Effects 0.000 claims description 26
- 238000012544 monitoring process Methods 0.000 claims description 24
- 238000012546 transfer Methods 0.000 claims description 15
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 claims description 10
- 238000004590 computer program Methods 0.000 claims description 8
- 238000005259 measurement Methods 0.000 claims description 7
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- 229910052757 nitrogen Inorganic materials 0.000 claims description 5
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- 230000005540 biological transmission Effects 0.000 abstract description 9
- 238000003860 storage Methods 0.000 description 9
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- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 1
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- 238000004458 analytical method Methods 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 229910052799 carbon Inorganic materials 0.000 description 1
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Classifications
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/26—Steam-separating arrangements
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K11/00—Plants characterised by the engines being structurally combined with boilers or condensers
- F01K11/02—Plants characterised by the engines being structurally combined with boilers or condensers the engines being turbines
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K17/00—Using steam or condensate extracted or exhausted from steam engine plant
- F01K17/02—Using steam or condensate extracted or exhausted from steam engine plant for heating purposes, e.g. industrial, domestic
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22G—SUPERHEATING OF STEAM
- F22G1/00—Steam superheating characterised by heating method
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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Abstract
The disclosure provides an external supply industrial steam production method, an external supply industrial steam production device and electronic equipment, which are applied to a pressurized water reactor nuclear power unit, wherein the method comprises the following steps: extracting a first part of steam from a main steam pipeline of a pressurized water reactor nuclear motor unit, conveying the first part of steam to a turbine, driving a steam compressor to process the first part of steam by the turbine, expanding and doing work in the turbine to obtain main steam, processing the main steam by a steam-water separator to obtain saturated water and separated steam, inputting the separated steam into the steam compressor for heating and pressurizing treatment according to steam demand information to obtain superheated steam, and inputting the superheated steam into a throttling device for treatment to obtain external industrial steam. According to the method and the device, part of high-grade heat energy of saturated steam can be used as input energy of the steam turbine to be converted into mechanical energy to apply work to the saturated steam, so that superheated steam with higher temperature and pressure is produced more efficiently to be used as external industrial steam, and the obtained external industrial steam is more suitable for long-distance transmission.
Description
Technical Field
The disclosure relates to the technical field of nuclear energy application, in particular to an external supply industrial steam production method, an external supply industrial steam production device and electronic equipment.
Background
Currently, steam is widely used in modern industry, mainly provided by a fossil fuel boiler, the use of a coal-fired boiler is limited in various places under the target pressure of double carbon, industrial steam supply is notched, nuclear energy multi-way application is mature along with the increasing number of nuclear power units and the continuous development of nuclear energy application technology, and the demand of society for nuclear energy steam is increased.
In the related art, heat exchange is generally performed by extracting two-circuit steam through a multi-stage heat exchanger to produce superheated steam for external use as industrial steam.
In this way, the limitation of parameters of industrial steam also limits the steam delivery distance and utilization.
Disclosure of Invention
The present disclosure aims to solve, at least to some extent, one of the technical problems in the related art.
Therefore, an object of the present disclosure is to provide an external industrial steam production method, an external industrial steam production device, an electronic apparatus, a storage medium, and a computer program product, which are applied to a pressurized water reactor nuclear power unit, and can convert part of high-grade heat energy of saturated steam as input energy of a steam turbine into mechanical energy to apply work to the saturated steam, so that superheated steam with higher temperature and pressure is produced more efficiently as external industrial steam, and the obtained external industrial steam is more suitable for long-distance transmission.
An embodiment of a first aspect of the present disclosure provides an external supply industrial steam production method, applied to a pressurized water reactor nuclear power unit, the method including: extracting a first part of steam from a main steam pipeline of a pressurized water reactor nuclear motor unit, conveying the first part of steam to a turbine, driving a steam compressor to process the first part of steam by the turbine, and expanding and acting the first part of steam in the turbine to obtain main steam; acquiring steam demand information, wherein the steam demand information describes a required steam pressure value, a required steam temperature value and a required steam demand of the industrial steam; treating the main steam by using a steam-water separator to obtain saturated water and separated steam; according to the steam demand information, the separated steam is input into a steam compressor for heating and pressurizing treatment to obtain superheated steam; and inputting the superheated steam into a throttling device for processing to obtain external industrial steam, wherein the steam pressure value, the steam temperature value and the steam demand of the external industrial steam meet the steam demand information.
According to the method for producing the external industrial steam, provided by the embodiment of the first aspect of the disclosure, the first part of steam is extracted from the main steam pipeline of the pressurized water reactor nuclear motor unit and is conveyed to the turbine, the turbine drives the steam compressor to process the first part of steam, the first part of steam expands in the turbine to do work to obtain main steam, and the steam demand information is obtained, wherein the steam demand information describes the required steam pressure value, the steam temperature value and the steam demand of the external industrial steam, the main steam is processed by the steam-water separator to obtain saturated water and separated steam, the separated steam is input into the steam compressor to be heated and pressurized according to the steam demand information, the superheated steam is input into the throttling device to be processed to obtain the external industrial steam, and the steam pressure value, the steam temperature value and the steam demand of the external industrial steam meet the steam demand information, so that part of high-grade heat energy of the saturated steam can be converted into mechanical energy to do work on the saturated steam, and the superheated steam with higher temperature pressure can be produced more efficiently as the external industrial steam, and the obtained external industrial steam is more suitable for long-distance transmission.
An embodiment of a second aspect of the present disclosure provides an external supply industrial steam production device, applied to a pressurized water reactor nuclear motor unit, the device comprising: the first processing module extracts a first part of steam from a main steam pipeline of the pressurized water reactor nuclear motor unit and transmits the first part of steam to the turbine, the turbine drives the steam compressor to process the first part of steam, and the first part of steam expands in the turbine to do work to obtain main steam; the first acquisition module is used for acquiring steam demand information, wherein the steam demand information describes a required steam pressure value, a required steam temperature value and a required steam demand of the industrial steam; the second treatment module is used for treating the main steam by utilizing the steam-water separator to obtain saturated water and separated steam; the third processing module is used for inputting the separated steam into the steam compressor for heating and pressurizing treatment according to the steam demand information to obtain superheated steam; and the fourth processing module is used for inputting the superheated steam into the throttling device for processing to obtain external industrial steam, wherein the steam pressure value, the steam temperature value and the steam demand of the external industrial steam meet the steam demand information.
According to the external supply industrial steam production device provided by the embodiment of the second aspect of the disclosure, the first part of steam is extracted from the main steam pipeline of the pressurized water reactor nuclear motor unit and is conveyed to the turbine, the turbine drives the steam compressor to process the first part of steam, the first part of steam is expanded in the turbine to do work to obtain main steam, and the steam demand information is obtained, wherein the steam demand information describes the required steam pressure value, the steam temperature value and the steam demand of the external supply industrial steam, the main steam is processed by the steam-water separator to obtain saturated water and separated steam, the separated steam is input into the steam compressor to be heated and pressurized according to the steam demand information, the superheated steam is input into the throttling device to be processed to obtain the external supply industrial steam, and the steam pressure value, the steam temperature value and the steam demand of the external supply industrial steam meet the steam demand information, so that part of high-grade heat energy of the saturated steam can be converted into mechanical energy to do work on the saturated steam, and the obtained superheated steam with higher temperature pressure can be used as the external supply industrial steam more efficiently, and the obtained external supply industrial steam is more suitable for long-distance transmission.
An embodiment of a third aspect of the present disclosure provides an electronic device, including a memory, a processor, and a computer program stored in the memory and capable of running on the processor, where the processor executes the program to implement an external industrial steam production method as set forth in the embodiment of the first aspect of the present disclosure.
An embodiment of a fourth aspect of the present disclosure proposes a non-transitory computer-readable storage medium, on which a computer program is stored, which program, when executed by a processor, implements an external industrial steam production method as proposed by an embodiment of the first aspect of the present disclosure.
A fifth aspect embodiment of the present disclosure proposes a computer program product which, when executed by a processor, performs an external industrial steam production method as proposed by the first aspect embodiment of the present disclosure.
Additional aspects and advantages of the disclosure will be set forth in part in the description which follows, and in part will be obvious from the description, or may be learned by practice of the disclosure.
Drawings
The foregoing and/or additional aspects and advantages of the present disclosure will become apparent and readily appreciated from the following description of the embodiments, taken in conjunction with the accompanying drawings, in which:
FIG. 1 is a schematic flow chart of an external industrial steam production method according to an embodiment of the disclosure;
FIG. 2 is a schematic flow chart of an external industrial steam production method according to another embodiment of the disclosure;
FIG. 3 is a schematic diagram of a pressurized water reactor nuclear steam superheating and radiation monitoring system in accordance with an embodiment of the present disclosure;
FIG. 4 is a schematic diagram of another pressurized water reactor nuclear steam superheating and radiation monitoring system in an embodiment of the disclosure;
FIG. 5 is a schematic flow chart of an external industrial steam production method according to another embodiment of the disclosure;
FIG. 6 is a schematic view of an external industrial steam production device according to an embodiment of the present disclosure;
FIG. 7 is a schematic view of an external industrial steam production device according to another embodiment of the present disclosure;
fig. 8 illustrates a block diagram of an exemplary electronic device suitable for use in implementing embodiments of the present disclosure.
Detailed Description
Embodiments of the present disclosure are described in detail below, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to like or similar elements or elements having like or similar functions throughout. The embodiments described below by referring to the drawings are exemplary only for explaining the present disclosure and are not to be construed as limiting the present disclosure. On the contrary, the embodiments of the disclosure include all alternatives, modifications, and equivalents as may be included within the spirit and scope of the appended claims.
Fig. 1 is a schematic flow chart of an external industrial steam production method according to an embodiment of the disclosure.
It should be noted that, the execution body of the method for producing industrial steam by external supply in this embodiment is an apparatus for producing industrial steam by external supply, and the apparatus may be implemented in software and/or hardware, and the apparatus may be configured in an electronic device, which is not limited thereto.
As shown in fig. 1, the method for producing the external industrial steam comprises the following steps:
s101: and extracting a first part of steam from a main steam pipeline of the pressurized water reactor nuclear motor unit, conveying the first part of steam to a turbine, driving a steam compressor to process the first part of steam by the turbine, and expanding and acting the first part of steam in the turbine to obtain main steam.
The main steam obtained after the treatment of driving the steam compressor by using the turbine is saturated steam.
The embodiment of the disclosure can be applied to a pressurized water reactor nuclear power unit, a loop of the pressurized water reactor nuclear power unit is positioned in a containment, a steam generator of the pressurized water reactor nuclear power unit is equipment connected with the loop and the loop, fluid in the loop circulates between a pressure container and the steam generator under the driving of a main pump, the heat of fission of a reactor core in the pressure container is transferred to the loop through the steam generator, saturated steam is generated at the secondary side of the steam generator, the saturated steam enters a high-pressure cylinder of a steam turbine, and after the steam is reheated by a steam-water separation reheater, the steam enters a low-pressure cylinder of the steam turbine to continuously apply work so as to push a generator to generate power.
In the embodiment of the disclosure, a part of steam can be extracted from the main steam pipeline as a first part of steam, the first part of steam is input into the turbine, the turbine is utilized to drive the steam compressor to increase the enthalpy reduced by the turbine steam into the steam passing through the steam compressor, the first part of steam expands in the turbine to do work to obtain main steam, the quality of the steam is improved, the processed main steam is obtained, the main steam is saturated steam, and the steam humidity of the main steam discharged after the turbine does work is increased.
S102: steam demand information is obtained, wherein the steam demand information describes a required steam pressure value, a steam temperature value and a steam demand of the industrial steam.
The steam demand information is data information for describing the steam pressure condition, the steam temperature value and the steam demand condition of the required external industrial steam.
For example, if the industrial enterprise has a large steam demand below 1.6MPa, the pressurized water reactor nuclear power unit mainly works in the wet steam area, and the exhaust pressure of the high pressure cylinder is lower than 1MPa, the steam pressure condition of the external industrial steam described in the steam demand information in the embodiment of the disclosure may be in a higher pressure range below 1.6 MPa.
In the implementation of the present disclosure, steam demand information may be obtained, where the steam demand information may describe a steam pressure demand range, a steam temperature value demand range, and a steam demand range, for example, the steam demand information may describe that the desired external industrial steam is low-pressure but high-demand steam, and may describe the desired external industrial steam temperature value demand range.
S103: and (5) treating the main steam by using a steam-water separator to obtain saturated water and separated steam.
In the embodiment of the disclosure, when the first part of steam extracted from the main steam pipeline of the pressurized water reactor nuclear motor unit is conveyed to the turbine, the turbine is utilized to drive the steam compressor to process the first part of steam, so as to obtain main steam and obtain steam demand information, and the steam separator can be utilized to process the main steam according to the steam demand information, so that saturated water and separated steam are obtained.
In the embodiment of the disclosure, when the steam-water separator is utilized to process the main steam, the main steam can be input into the steam-water separator for processing, so that saturated water separated after the steam separator is utilized to process and separated steam is obtained.
In other embodiments, part of steam discharged by the high-pressure cylinder of the steam turbine can be extracted and conveyed to a steam-water separator together with the main steam to be treated to obtain the separated saturated water and separated steam.
S104: and according to the steam demand information, inputting the separated steam into a steam compressor for heating and pressurizing treatment to obtain superheated steam.
According to the embodiment of the disclosure, after the main steam is processed by the steam-water separator according to the steam demand information to obtain saturated water and separated steam, the separated saturated water can be processed in the deaerator or the feedwater heater, and the separated steam is input into the steam compressor for heating and boosting treatment to obtain superheated steam.
In other embodiments, when the steam demand information indicates that the required steam pressure of the external industrial steam is low but the required steam demand is large, the steam exhausted by the high-pressure cylinder of the partial turbine is extracted, and is conveyed to the saturated water and the separated steam after being treated in the steam-water separator together with the main steam, and the obtained separated steam is input to the steam compressor for heating and boosting treatment, so that superheated steam is obtained.
S105: and inputting the superheated steam into a throttling device for processing to obtain external industrial steam, wherein the steam pressure value, the steam temperature value and the steam demand of the external industrial steam meet the steam demand information.
According to the embodiment of the disclosure, after the separated steam is input into the steam compressor for heating and pressurizing treatment to obtain the superheated steam, the superheated steam can be input into the throttling device for treatment to obtain the external supply industrial steam, and the pressure and temperature parameters of the external supply industrial steam obtained after the treatment of the throttling device both meet the requirement parameters of external supply steam.
In this embodiment, a first part of steam is extracted from a main steam pipeline of a pressurized water reactor nuclear motor unit and is conveyed to a turbine, the turbine drives a steam compressor to process the first part of steam, the first part of steam expands in the turbine to obtain main steam, steam demand information is obtained, wherein the steam demand information describes a required steam pressure value, a steam temperature value and a steam demand of external supply industrial steam, a steam-water separator is utilized to process the main steam to obtain saturated water and separated steam, the separated steam is input into the steam compressor to perform heating and pressurizing treatment according to the steam demand information to obtain superheated steam, the superheated steam is input into a throttling device to perform treatment to obtain external supply industrial steam, and the steam pressure value, the steam temperature value and the steam demand of the external supply industrial steam meet the steam demand information.
Fig. 2 is a schematic flow chart of an external industrial steam production method according to another embodiment of the disclosure.
As shown in fig. 2, the method for producing the external supply industrial steam comprises the following steps:
s201: and extracting a first part of steam from a main steam pipeline of the pressurized water reactor nuclear motor unit, conveying the first part of steam to a turbine, driving a steam compressor to process the first part of steam by the turbine, and expanding and acting the first part of steam in the turbine to obtain main steam.
S202: steam demand information is obtained, wherein the steam demand information describes a required steam pressure value, a steam temperature value and a steam demand of the industrial steam.
S203: and (5) treating the main steam by using a steam-water separator to obtain saturated water and separated steam.
The above embodiments can be seen from the specific description of S201 to S203, and will not be repeated here.
S204: if the steam demand information indicates that the required external industrial steam is a first steam pressure value, a first steam temperature value and a first demand, the separated steam is obtained after the main steam is treated by the steam-water separator.
In an embodiment of the disclosure, if the steam demand information indicates that the required external industrial steam is a first steam pressure value, a first steam temperature value and a first demand, where the first steam pressure value and the first demand are a higher steam pressure value and a lower steam demand, and the first steam temperature value is a steam temperature value corresponding to the first steam pressure value and the first demand, the separated steam is separated steam obtained after the main steam is sent to the steam-water separator for processing.
For example, as shown in fig. 3, fig. 3 is a schematic structural diagram of a pressurized water reactor nuclear steam superheating and radiation monitoring system according to an embodiment of the disclosure, where reference numeral 1 is a containment vessel, reference numeral 2 is a pressure vessel, reference numeral 3 is a steam generator, reference numeral 4 is a turbine high-pressure cylinder, reference numeral 5 is a steam-water separation reheater, reference numeral 6 is a turbine low-pressure cylinder, reference numeral 7 is a generator, reference numeral 11 is a cooler, reference numeral 21 is a turbine, and reference numeral 22 is a steam-water separator; 23 is a steam compressor, 24 is a throttling device, 25 is a buffer tank, 31 and 32 are quick-closing valves, a part of steam is extracted from a main steam pipeline and is used as a first part of steam to enter a turbine 21, the turbine 21 drives the steam compressor 23, the enthalpy reduced by the steam of the turbine 21 is increased to the steam passing through the steam compressor 23, the quality of the steam is improved, the main steam is saturated steam, the humidity of the main steam discharged after the turbine 21 works is increased, the main steam can be conveyed to a steam-water separator 22 for processing, saturated water and separated steam are obtained, the saturated water separated by the steam-water separator 22 is removed from an oxygen separator or a feed water heater, the separated steam enters the steam compressor 23 for heating and boosting treatment, superheated steam is obtained, the superheated steam is conveyed to the throttling device 24 for processing, and external industrial steam with pressure and temperature parameters meeting external supply is obtained.
S205: if the steam demand information indicates that the required external industrial steam is a second steam pressure value, a second steam temperature value and a second demand, the separated steam is obtained after the main steam and the second part of steam are treated by a steam-water separator, wherein the second part of steam is extracted from the exhaust steam of the high-pressure cylinder of the steam turbine.
The second part of steam is extracted from the exhaust steam of the high-pressure cylinder of the steam turbine.
In the embodiment of the disclosure, if the steam demand information indicates that the required external industrial steam is a second steam pressure value, a second steam temperature value and a second demand, part of steam can be extracted from the exhaust steam of the high-pressure cylinder of the steam turbine as second part of steam, and the second part of steam and the main steam are conveyed to a steam-water separator together for treatment, so that saturated water and separated steam are obtained.
For example, as shown in fig. 4, fig. 4 is a schematic structural diagram of another nuclear steam superheating and radiation monitoring system of a pressurized water reactor according to an embodiment of the disclosure, in which part of the steam discharged from the high-pressure cylinder 4 of the turbine may be extracted, and after entering the steam compressor 23 through the steam-water separator 22 together with the main steam discharged from the turbine 21 to be superheated, the external industrial steam with pressure and temperature parameters satisfying the external supply is obtained through the throttling device 24.
Optionally, in some embodiments, the second vapor pressure value is less than the first vapor pressure value and the second demand is greater than the first demand.
S206: and inputting the separated steam into a steam compressor for heating and pressurizing treatment to obtain superheated steam.
S207: and inputting the superheated steam into a throttling device for processing to obtain external industrial steam, wherein the steam pressure value and the steam demand of the external industrial steam meet the steam demand information.
The descriptions of S206 and S207 may be referred to the above embodiments, and are not repeated here.
In this embodiment, the first part of steam is extracted from the main steam pipeline of the pressurized water reactor nuclear motor unit and is conveyed to the turbine, the turbine drives the steam compressor to process the first part of steam, the first part of steam is expanded in the turbine to obtain main steam, and steam demand information is obtained, wherein the steam demand information describes a required steam pressure value, a steam temperature value and a steam demand of external industrial steam, the main steam is processed by using the steam-water separator to obtain saturated water and separated steam, the separated steam is input into the steam compressor to perform heating and pressurizing treatment according to the steam demand information, superheated steam is input into the throttling device to perform treatment, the external industrial steam is obtained, wherein the steam pressure value, the steam temperature value and the steam demand of the external industrial steam meet the steam demand information, and the high-grade heat energy of the part of saturated steam can be converted into mechanical energy to perform work on the saturated steam, so that the obtained external industrial steam is more suitable for remote transmission, the method provided by the embodiment of the present disclosure can be used for remote transmission of the external industrial steam, the thermal energy is not required by the traditional industrial steam pressure system, and the thermal energy is more suitable for remote transmission of the saturated steam, and the thermal energy is more efficient, and the thermal energy is more suitable for remote transmission of the industrial steam is produced by the traditional thermal energy.
Fig. 5 is a schematic flow chart of an external industrial steam production method according to another embodiment of the disclosure.
As shown in fig. 5, the method for producing the external supply industrial steam comprises the following steps:
s501: and extracting a first part of steam from a main steam pipeline of the pressurized water reactor nuclear motor unit, conveying the first part of steam to a turbine, driving a steam compressor to process the first part of steam by the turbine, and expanding and acting the first part of steam in the turbine to obtain main steam.
S502: steam demand information is obtained, wherein the steam demand information describes a required steam pressure value, a steam temperature value and a steam demand of the industrial steam.
S503: and (5) treating the main steam by using a steam-water separator to obtain saturated water and separated steam.
S504: and according to the steam demand information, inputting the separated steam into a steam compressor for heating and pressurizing treatment to obtain superheated steam.
S505: and inputting the superheated steam into a throttling device for processing to obtain external industrial steam, wherein the steam pressure value, the steam temperature value and the steam demand of the external industrial steam meet the steam demand information.
The specific description of S501 to S505 may be referred to the above embodiments, and will not be repeated here.
S506: and setting a radiation monitoring instrument to monitor the radioactivity of a secondary loop of the pressurized water reactor nuclear power unit and obtain a radioactivity measurement value, wherein the radiation monitoring instrument is arranged beside an outer heat insulation layer pipe of a sewage pipeline between the cooler and the steam generator.
Wherein, the radiation monitoring instrument is arranged beside the heat preservation outer pipe of the sewage pipeline between the cooler and the steam generator.
In the embodiment of the disclosure, a radiation monitoring instrument can be arranged beside an outer tube of a heat insulation layer of a drain pipe between a cooler and a steam generator to monitor the radioactivity of a secondary loop of a pressurized water reactor nuclear power unit, a method of combining the existing radiation monitoring instrument for monitoring the radioactivity of the secondary loop and a newly added radiation monitoring instrument of the secondary loop of a nuclear power plant can be adopted to realize reliable, redundant and quick monitoring on the leakage of a primary loop heat transfer pipe and a secondary loop radioactivity, each steam generator of the pressurized water reactor nuclear power unit is connected with a drain pipe, radioactive substances discharged by the steam generator enter a continuous electric desalting technology module (EDI) for treatment through the cooler, certain gas-water distribution exists in the process of converting the radioactive substances from a liquid phase into a gas phase in the steam generator, and in the process of conservative analysis, the gas-water distribution factor of iodine is considered to be 100, and the gas-water distribution factor of aerosol is 200, so that the radioactivity concentration of a fluid of the drain pipe of the steam generator is 100 times that of steam condensate water, and the radioactivity of the steam generator can be monitored more sensitively.
For example, as shown in fig. 4, in order to shorten the distance from the steam generator 3 to the radiation monitoring instrument as much as possible to realize rapid measurement, a redundant radiation monitoring instrument 32 is added at a position as close as possible to the containment in the auxiliary factory building in front of the cooler 11, so that the measurement reliability can be improved by adopting a redundant configuration, because the measured object is high-temperature liquid, the detector cannot be immersed in the measured liquid, and the response time of the instrument is required to be shorter, the high-temperature liquid needs to be cooled for a longer time, so that the detection efficiency is increased by adopting a mode of measuring beside the outer tube of the heat insulation layer of the drain pipeline of the steam generator, the background of the detector is reduced by adopting a mode of wrapping lead shielding, the detection lower limit is reduced, and the response time is reduced.
S507: and closing the quick-closing valve of the industrial steam system under the condition that the measured value of the radioactivity is larger than or equal to a preset radioactivity threshold value.
In the embodiment of the disclosure, a preset radioactivity threshold value can be preset to perform real-time monitoring processing on the radioactivity measured value, the radioactivity measured value and the preset radioactivity threshold value can be compared with each other, and if the radioactivity measured value is greater than or equal to the preset radioactivity threshold value, a quick-closing valve of the industrial steam system is closed to prevent radioactive substances from leaking.
S508: a nitrogen sixteen N-16 radiation detector is arranged at a steam outlet pipeline of a steam generator of a pressurized water reactor nuclear power unit so as to detect the actual measurement leakage rate of a heat transfer pipe of the steam generator.
The actually measured leakage rate is leakage rate data obtained by detecting the leakage rate of the heat transfer pipe in real time by using a nitrogen sixteen-radiation detector.
In embodiments of the present disclosure, a nitrogen sixteen (N-16) radiation detector may be provided at the steam outlet pipe of each steam generator of a pressurized water reactor nuclear power plant to detect the leak rate of the steam generator heat transfer tubes.
S509: and acquiring a preset leakage rate threshold.
The preset leakage rate threshold value refers to a leakage rate threshold value preset for a heat transfer tube of the steam generator, and the preset leakage rate can be adaptively set according to the field operation condition.
In the embodiment of the disclosure, the pure generator set allows the heat transfer tube of the steam generator to have a certain leakage rate, so that the existing alarm value does not meet the requirement of externally supplied industrial steam, a lower alarm value needs to be improved and added, and a proper alarm value can be set as a preset leakage rate threshold according to the field operation condition of the nuclear power plant.
S510: and carrying out early warning treatment on the leakage condition of the heat transfer pipe of the steam generator according to the actually measured leakage rate and the preset leakage rate threshold value.
In the embodiment of the disclosure, when the leakage condition of the heat transfer tube of the steam generator is pre-warned according to the actually measured leakage rate and the preset leakage rate threshold value, the actually measured leakage rate and the preset leakage rate threshold value can be subjected to numerical comparison, and if the actually measured leakage rate is greater than or equal to the preset leakage rate threshold value, the alarm processing can be performed, so that the leakage rate of the heat transfer tube possibly causes a subsequent risk event.
Optionally, in some embodiments, the quick-shut valve of the industrial steam system is triggered to close if the measured leak rate is greater than or equal to a preset leak rate threshold.
In the embodiment of the disclosure, any one of the existing radiation monitoring instrument for monitoring the radioactivity of the secondary loop and the newly added radiation monitoring instrument of the nuclear power plant alarms, and the industrial steam quick-closing valves 31 and 32 are triggered to be closed, so that the purpose of redundant configuration of the quick-closing valves is to ensure reliable closing and isolation and prevent radionuclide from leaving the factory.
Optionally, in some embodiments, a surge tank is provided between the throttle device and the quick-closing valve.
Wherein the buffer tank may be used to reduce the flow rate of the blowdown stream.
In the embodiment of the disclosure, a buffer tank can be arranged between the throttling device and the quick-closing valve so as to reduce the flow speed of the sewage flow and prevent the radionuclide from leaving the factory.
For example, the blowdown stream may take time from the steam generator to the radiation monitor 32, and the radiation detector response, signal processing transmission, and valve closing may take time, the pipe diameter of the industrial steam pipe in the nuclear power plant may be increased reasonably to reduce the steam flow rate, and the buffer tank 25 may be provided to retain the steam in the plant for a period of time to ensure that there is sufficient time to isolate the steam in the plant once radioactivity is detected.
In the embodiment, a first part of steam is extracted from a main steam pipeline of a pressurized water reactor nuclear motor unit and is conveyed to a turbine, the turbine drives a steam compressor to process the first part of steam, the first part of steam expands in the turbine to obtain main steam, steam demand information is obtained, wherein the steam demand information describes a steam pressure value, a steam temperature value and a steam demand of external industrial steam required by the description, a steam-water separator is utilized to process the main steam to obtain saturated water and separated steam, the separated steam is input into the steam compressor for heating and pressurizing treatment according to the steam demand information to obtain superheated steam, the superheated steam is input into a throttling device for treatment to obtain the external industrial steam, the steam pressure value, the steam temperature value and the steam demand of the external industrial steam meet the steam demand information, the method for producing the external supply industrial steam provided by the embodiment of the disclosure designs a reliable and rapid radiation monitoring scheme to form a reliable isolation industrial steam network for detecting leakage of a heat transfer tube of a steam generator, enables a pressurized water reactor unit to have feasibility in the technology of directly externally supplying steam, provides a reliable production scheme for nuclear energy steam supply, utilizes the distribution proportion of steam-water radioactivity in a steam nuclide generator, measures radioactivity of sewage discharged by the steam generator, sensitively monitors radioactivity concentration of the steam, ensure that the radioactivity of the externally supplied industrial steam meets the radiation protection target.
Fig. 6 is a schematic structural view of an external industrial steam production device according to an embodiment of the present disclosure.
As shown in fig. 6, the external supply industrial steam generating device 60 includes:
the first processing module 601 is configured to extract a first part of steam from a main steam pipeline of the pressurized water reactor nuclear motor unit, send the first part of steam to a turbine, and drive a steam compressor to process the first part of steam by the turbine, where the first part of steam expands in the turbine to perform work to obtain main steam;
a first obtaining module 602, configured to obtain steam demand information, where the steam demand information describes a required steam pressure value, a required steam temperature value, and a required steam demand of the industrial steam;
a second processing module 603, configured to process the main steam with a steam-water separator to obtain saturated water and separated steam;
the third processing module 604 is configured to input the separated steam into the steam compressor for heating and pressurizing according to the steam demand information, so as to obtain superheated steam;
the fourth processing module 605 is configured to input superheated steam into the throttling device for processing, so as to obtain external industrial steam, where the steam pressure value, the steam temperature value and the steam demand of the external industrial steam meet the steam demand information.
In some embodiments of the present disclosure, the third processing module 604 is specifically configured to:
if the steam demand information indicates that the required external industrial steam is a first steam pressure value, a first steam temperature value and a first demand, the separated steam is obtained after the steam-water separator is used for treating main steam;
if the steam demand information indicates that the required external industrial steam is a second steam pressure value, a second steam temperature value and a second demand, the separated steam is obtained after the steam-water separator processes the main steam and a second part of steam, wherein the second part of steam is extracted from the exhaust steam of a high-pressure cylinder of the steam turbine;
and inputting the separated steam into the steam compressor for heating and pressurizing treatment to obtain superheated steam.
In some embodiments of the present disclosure, wherein the second vapor pressure value is less than the first vapor pressure value, the second demand is greater than the first demand.
In some embodiments of the present disclosure, as shown in fig. 7, fig. 7 is a schematic structural diagram of an external industrial steam production device according to another embodiment of the present disclosure, and further includes:
the monitoring module 606 is used for setting a radiation monitoring instrument to monitor the radioactivity of the secondary loop of the pressurized water reactor nuclear power unit to obtain a radioactivity measurement value, wherein the radiation monitoring instrument is arranged beside an outer tube of an insulating layer of a sewage pipeline between the cooler and the steam generator;
The fifth processing module 607 closes the quick-shut valve of the industrial steam system if the radioactivity measurement is greater than or equal to a preset radioactivity threshold.
In some embodiments of the present disclosure, further comprising:
a sixth processing module 608, configured to set a nitrogen sixteen N-16 radiation detector at a steam outlet pipe of a steam generator of the pressurized water reactor nuclear power unit, so as to detect an actually measured leakage rate of a heat transfer pipe of the steam generator;
a second obtaining module 609, configured to obtain a preset leak rate threshold;
and a seventh processing module 610, configured to perform early warning processing on the leakage condition of the heat transfer tube of the steam generator according to the actually measured leakage rate and the preset leakage rate threshold.
In some embodiments of the present disclosure, the seventh processing module 610 is specifically configured to:
and triggering to close a quick-closing valve of the pressurized water reactor nuclear power industrial steam system under the condition that the measured leakage rate is greater than or equal to a preset leakage rate threshold value.
In some embodiments of the present disclosure, there is a surge tank between the throttle device and the quick-closing valve.
Corresponding to the external industrial steam production method provided by the embodiments of fig. 1 to 5, the present disclosure also provides an external industrial steam production device, and since the external industrial steam production device provided by the embodiments of the present disclosure corresponds to the external industrial steam production method provided by the embodiments of fig. 1 to 5, the implementation of the external industrial steam production method is also applicable to the external industrial steam production device provided by the embodiments of the present disclosure, which is not described in detail in the embodiments of the present disclosure.
In this embodiment, a first part of steam is extracted from a main steam pipeline of a pressurized water reactor nuclear motor unit and is conveyed to a turbine, the turbine drives a steam compressor to process the first part of steam, the first part of steam expands in the turbine to obtain main steam, steam demand information is obtained, wherein the steam demand information describes a required steam pressure value, a steam temperature value and a steam demand of external supply industrial steam, a steam-water separator is utilized to process the main steam to obtain saturated water and separated steam, the separated steam is input into the steam compressor to perform heating and pressurizing treatment according to the steam demand information to obtain superheated steam, the superheated steam is input into a throttling device to perform treatment to obtain external supply industrial steam, and the steam pressure value, the steam temperature value and the steam demand of the external supply industrial steam meet the steam demand information.
In order to implement the above-described embodiments, the present disclosure also proposes a non-transitory computer-readable storage medium having stored thereon a computer program which, when executed by a processor, implements an external industrial steam production method as proposed in the foregoing embodiments of the present disclosure.
To achieve the above embodiments, the present disclosure also proposes a computer program product which, when executed by an instruction processor in the computer program product, performs the method for producing industrial steam as proposed in the foregoing embodiments of the present disclosure.
Fig. 8 illustrates a block diagram of an exemplary electronic device suitable for use in implementing embodiments of the present disclosure.
The computer device 12 shown in fig. 8 is merely an example and should not be construed as limiting the functionality and scope of use of the disclosed embodiments.
As shown in FIG. 8, the computer device 12 is in the form of a general purpose computing device. Components of computer device 12 may include, but are not limited to: one or more processors or processing units 16, a system memory 28, a bus 18 that connects the various system components, including the system memory 28 and the processing units 16.
Bus 18 represents one or more of several types of bus structures, including a memory bus or memory controller, a peripheral bus, an accelerated graphics port, a processor, and a local bus using any of a variety of bus architectures. By way of example, and not limitation, such architectures include industry Standard architecture (Industry Standard Architecture; hereinafter ISA) bus, micro channel architecture (Micro Channel Architecture; hereinafter MAC) bus, enhanced ISA bus, video electronics standards Association (Video Electronics Standards Association; hereinafter VESA) local bus, and peripheral component interconnect (Peripheral Component Interconnection; hereinafter PCI) bus.
Computer device 12 typically includes a variety of computer system readable media. Such media can be any available media that is accessible by computer device 12 and includes both volatile and nonvolatile media, removable and non-removable media.
Memory 28 may include computer system readable media in the form of volatile memory, such as random access memory (Random Access Memory; hereinafter: RAM) 30 and/or cache memory 32. The computer device 12 may further include other removable/non-removable, volatile/nonvolatile computer system storage media. By way of example only, storage system 34 may be used to read from or write to non-removable, nonvolatile magnetic media (not shown in FIG. 8, commonly referred to as a "hard disk drive").
Although not shown in fig. 8, a magnetic disk drive for reading from and writing to a removable non-volatile magnetic disk (e.g., a "floppy disk"), and an optical disk drive for reading from or writing to a removable non-volatile optical disk (e.g., a compact disk read only memory (Compact Disc Read Only Memory; hereinafter CD-ROM), digital versatile read only optical disk (Digital Video Disc Read Only Memory; hereinafter DVD-ROM), or other optical media) may be provided. In such cases, each drive may be coupled to bus 18 through one or more data medium interfaces. Memory 28 may include at least one program product having a set (e.g., at least one) of program modules configured to carry out the functions of the various embodiments of the disclosure.
A program/utility 40 having a set (at least one) of program modules 42 may be stored in, for example, memory 28, such program modules 42 including, but not limited to, an operating system, one or more application programs, other program modules, and program data, each or some combination of which may include an implementation of a network environment. Program modules 42 generally perform the functions and/or methods in the embodiments described in this disclosure.
The computer device 12 may also communicate with one or more external devices 14 (e.g., keyboard, pointing device, display 24, etc.), one or more devices that enable a person to interact with the computer device 12, and/or any devices (e.g., network card, modem, etc.) that enable the computer device 12 to communicate with one or more other computing devices. Such communication may occur through an input/output (I/O) interface 22. Moreover, the computer device 12 may also communicate with one or more networks such as a local area network (Local Area Network; hereinafter LAN), a wide area network (Wide Area Network; hereinafter WAN) and/or a public network such as the Internet via the network adapter 20. As shown, network adapter 20 communicates with other modules of computer device 12 via bus 18. It should be appreciated that although not shown, other hardware and/or software modules may be used in connection with computer device 12, including, but not limited to: microcode, device drivers, redundant processing units, external disk drive arrays, RAID systems, tape drives, data backup storage systems, and the like.
The processing unit 16 performs various functional applications and parameter information determination by running a program stored in the system memory 28, for example, implementing the off-line industrial steam production method mentioned in the foregoing embodiment.
It should be noted that in the description of the present disclosure, the terms "first," "second," and the like are used for descriptive purposes only and are not to be construed as indicating or implying relative importance. Furthermore, in the description of the present disclosure, unless otherwise indicated, the meaning of "a plurality" is two or more.
Any process or method descriptions in flow charts or otherwise described herein may be understood as representing modules, segments, or portions of code which include one or more executable instructions for implementing specific logical functions or steps of the process, and further implementations are included within the scope of the preferred embodiment of the present disclosure in which functions may be executed out of order from that shown or discussed, including substantially concurrently or in reverse order, depending on the functionality involved, as would be understood by those reasonably skilled in the art of the embodiments of the present disclosure.
It should be understood that portions of the present disclosure may be implemented in hardware, software, firmware, or a combination thereof. In the above-described embodiments, the various steps or methods may be implemented in software or firmware stored in a memory and executed by a suitable instruction execution system. For example, if implemented in hardware, as in another embodiment, may be implemented using any one or combination of the following techniques, as is well known in the art: discrete logic circuits having logic gates for implementing logic functions on data signals, application specific integrated circuits having suitable combinational logic gates, programmable Gate Arrays (PGAs), field Programmable Gate Arrays (FPGAs), and the like.
Those of ordinary skill in the art will appreciate that all or a portion of the steps carried out in the method of the above-described embodiments may be implemented by a program to instruct related hardware, where the program may be stored in a computer readable storage medium, and where the program, when executed, includes one or a combination of the steps of the method embodiments.
Furthermore, each functional unit in the embodiments of the present disclosure may be integrated in one processing module, or each unit may exist alone physically, or two or more units may be integrated in one module. The integrated modules may be implemented in hardware or in software functional modules. The integrated modules may also be stored in a computer readable storage medium if implemented in the form of software functional modules and sold or used as a stand-alone product.
The above-mentioned storage medium may be a read-only memory, a magnetic disk or an optical disk, or the like.
In the description of the present specification, a description referring to terms "one embodiment," "some embodiments," "examples," "specific examples," or "some examples," etc., means that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the present disclosure. In this specification, schematic representations of the above terms do not necessarily refer to the same embodiments or examples. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples.
Although embodiments of the present disclosure have been shown and described above, it will be understood that the above embodiments are illustrative and not to be construed as limiting the present disclosure, and that variations, modifications, alternatives, and variations may be made to the above embodiments by one of ordinary skill in the art within the scope of the present disclosure.
Claims (9)
1. An external supply industrial steam production method, which is applied to a pressurized water reactor nuclear motor unit, comprising:
extracting a first part of steam from a main steam pipeline of a pressurized water reactor nuclear motor unit, and conveying the first part of steam to a turbine, wherein the turbine drives a steam compressor to process the first part of steam, and the first part of steam expands in the turbine to do work so as to obtain main steam;
acquiring steam demand information, wherein the steam demand information describes a required steam pressure value, a steam temperature value and a steam demand of the industrial steam;
the main steam is treated by a steam-water separator to obtain saturated water and separated steam;
according to the steam demand information, the separated steam is input into the steam compressor for heating and pressurizing treatment to obtain superheated steam;
and inputting the superheated steam into a throttling device for processing to obtain external industrial steam, wherein the steam pressure value, the steam temperature value and the steam demand of the external industrial steam meet the steam demand information.
2. The method of claim 1, wherein said inputting said separated steam into said vapor compressor for heating and pressurizing according to said steam demand information to obtain superheated steam comprises:
if the steam demand information indicates that the required external industrial steam is a first steam pressure value, a first steam temperature value and a first demand, the separated steam is obtained after the steam-water separator processes main steam;
if the steam demand information indicates that the required external industrial steam is a second steam pressure value, a second steam temperature value and a second demand, the separated steam is obtained after the steam-water separator processes the main steam and a second part of steam, wherein the second part of steam is extracted from the exhaust steam of the high-pressure cylinder of the steam turbine;
and inputting the separated steam into the steam compressor for heating and pressurizing treatment to obtain superheated steam.
3. The method of claim 2, wherein the second vapor pressure value is less than the first vapor pressure value, and the second demand is greater than the first demand.
4. The method as recited in claim 1, further comprising:
a radiation monitoring instrument is arranged to monitor the radioactivity of the two loops of the pressurized water reactor nuclear power unit to obtain a radioactivity measured value, wherein the radiation monitoring instrument is arranged beside an outer heat insulation layer pipe of a sewage pipeline between a cooler and a steam generator;
and closing a quick-closing valve of the industrial steam system under the condition that the measured value of the radioactivity is larger than or equal to a preset radioactivity threshold value.
5. The method as recited in claim 4, further comprising:
arranging a nitrogen sixteen N-16 radiation detector at a steam outlet pipeline of a steam generator of the pressurized water reactor nuclear power unit to detect the actual measurement leakage rate of a heat transfer pipe of the steam generator;
acquiring a preset leakage rate threshold value;
and carrying out early warning treatment on the leakage condition of the heat transfer pipe of the steam generator according to the actually measured leakage rate and the preset leakage rate threshold value.
6. The method of claim 5, wherein said pre-warning the leakage condition of the heat transfer tube of the steam generator based on the measured leakage rate and the preset leakage rate threshold value comprises:
And triggering to close a quick-closing valve of the industrial steam system under the condition that the measured leakage rate is larger than or equal to the preset leakage rate threshold value.
7. The method of claim 6, wherein a buffer tank is provided between the throttling device and the quick-closing valve.
8. An external supply industrial steam production device, characterized in that it is applied to pressurized water reactor nuclear power unit, said device includes:
the first processing module extracts a first part of steam from a main steam pipeline of the pressurized water reactor nuclear motor unit and transmits the first part of steam to the turbine, the turbine drives the steam compressor to process the first part of steam, and the first part of steam expands in the turbine to do work to obtain main steam;
the system comprises a first acquisition module, a second acquisition module and a control module, wherein the first acquisition module is used for acquiring steam demand information, and the steam demand information describes a required steam pressure value, a steam temperature value and a steam demand of external industrial steam;
the second treatment module is used for treating the main steam by utilizing a steam-water separator to obtain saturated water and separated steam;
the third processing module is used for inputting the separated steam into the steam compressor for heating and pressurizing treatment according to the steam demand information to obtain superheated steam;
And the fourth processing module is used for inputting the superheated steam into the throttling device for processing to obtain external industrial steam, wherein the steam pressure value, the steam temperature value and the steam demand of the external industrial steam meet the steam demand information.
9. An electronic device, comprising:
a memory, a processor and a computer program stored on the memory and executable on the processor, which processor, when executing the program, implements the method for producing off-board industrial steam according to any one of claims 1-7.
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| CN202310402161.2A CN116480433A (en) | 2023-04-11 | 2023-04-11 | Method and device for producing externally supplied industrial steam and electronic equipment |
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