CN117346133A - Nuclear energy steam supply system and supply method - Google Patents
Nuclear energy steam supply system and supply method Download PDFInfo
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- CN117346133A CN117346133A CN202311406170.5A CN202311406170A CN117346133A CN 117346133 A CN117346133 A CN 117346133A CN 202311406170 A CN202311406170 A CN 202311406170A CN 117346133 A CN117346133 A CN 117346133A
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- pressure gauge
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- flash evaporator
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- 238000000034 method Methods 0.000 title claims abstract description 14
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 137
- 238000012544 monitoring process Methods 0.000 claims abstract description 33
- 239000007788 liquid Substances 0.000 claims description 13
- 238000001704 evaporation Methods 0.000 claims description 5
- 230000008020 evaporation Effects 0.000 claims description 5
- 230000002285 radioactive effect Effects 0.000 claims description 2
- 230000008569 process Effects 0.000 description 5
- 230000001502 supplementing effect Effects 0.000 description 4
- 239000000463 material Substances 0.000 description 3
- 238000000926 separation method Methods 0.000 description 3
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 2
- 238000004891 communication Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- 238000009776 industrial production Methods 0.000 description 2
- 238000002955 isolation Methods 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 239000001301 oxygen Substances 0.000 description 2
- 229910052760 oxygen Inorganic materials 0.000 description 2
- 239000000941 radioactive substance Substances 0.000 description 2
- 238000004064 recycling Methods 0.000 description 2
- 230000004044 response Effects 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 description 1
- 239000004566 building material Substances 0.000 description 1
- 238000011033 desalting Methods 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000000605 extraction Methods 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 239000005431 greenhouse gas Substances 0.000 description 1
- 239000011261 inert gas Substances 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 239000013535 sea water Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 239000004753 textile Substances 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
- 229910052722 tritium Inorganic materials 0.000 description 1
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
- F22B37/42—Applications, arrangements, or dispositions of alarm or automatic safety devices
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B35/00—Control systems for steam boilers
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22D—PREHEATING, OR ACCUMULATING PREHEATED, FEED-WATER FOR STEAM GENERATION; FEED-WATER SUPPLY FOR STEAM GENERATION; CONTROLLING WATER LEVEL FOR STEAM GENERATION; AUXILIARY DEVICES FOR PROMOTING WATER CIRCULATION WITHIN STEAM BOILERS
- F22D1/00—Feed-water heaters, i.e. economisers or like preheaters
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22D—PREHEATING, OR ACCUMULATING PREHEATED, FEED-WATER FOR STEAM GENERATION; FEED-WATER SUPPLY FOR STEAM GENERATION; CONTROLLING WATER LEVEL FOR STEAM GENERATION; AUXILIARY DEVICES FOR PROMOTING WATER CIRCULATION WITHIN STEAM BOILERS
- F22D1/00—Feed-water heaters, i.e. economisers or like preheaters
- F22D1/50—Feed-water heaters, i.e. economisers or like preheaters incorporating thermal de-aeration of feed-water
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Combustion & Propulsion (AREA)
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
Abstract
The invention provides a nuclear energy steam supply system and a supply method, wherein the system comprises: the device comprises a first-stage preheater, a second-stage preheater, a feed water heater, a deaerator and a flash evaporator, wherein a first pressure gauge is connected between a second loop outlet of the second-stage preheater and a second loop inlet of the first-stage preheater; the high-temperature steam pipeline is connected with a third pressure gauge, and a three-loop inlet of the feed water heater is connected with a three-loop outlet of the secondary preheater; the water inlet of the flash evaporator is connected with the three-loop outlet of the feed water heater, a fourth pressure gauge, a radioactivity monitoring instrument and a second control valve are connected between the three-loop outlet of the feed water heater and the water inlet of the flash evaporator, and the steam outlet of the flash evaporator is connected with a user end through a pipeline. The invention can avoid the risk of nuclear leakage during the steam supply.
Description
Technical Field
The invention relates to the technical field of industrial steam supply, in particular to a nuclear energy steam supply system and a nuclear energy steam supply method.
Background
Steam is one of the indispensable production materials in numerous industrial production, and is widely applied to the industries of chemical industry, food, textile, building material manufacturing and the like. Industrial production requires large amounts of steam, and fossil energy is often an important source for providing steam, such as by steam extraction from thermal power plants or steam supply from self-contained boilers for industrial users. However, the use of fossil energy inevitably generates emission of greenhouse gases. Nuclear energy is used as clean, efficient and stable energy source and can continuously provide energy for users, but at present, the nuclear energy mainly generates electricity.
At present, the nuclear power plant mainly adopts a pressurized water reactor nuclear power technology, and compared with a thermal power plant and a high-temperature gas cooled reactor nuclear power plant, parameters of steam generated by the pressurized water reactor nuclear power plant are lower, such as temperature, pressure and the like. Moreover, the heat transfer pipe of the pressurized water reactor nuclear power plant steam generator has the possibility of leakage, so that the secondary loop possibly has certain radioactivity, and the secondary loop steam cannot be directly supplied to industrial users. The use of two-circuit steam through a heat exchanger to heat the feedwater is also contemplated in the art, but the heat exchanger still has the potential for leaks.
Disclosure of Invention
The present invention aims to solve at least one of the technical problems in the related art to some extent. Therefore, the embodiment of the invention provides a nuclear energy steam supply system and a nuclear energy steam supply method, which can avoid the risk of nuclear leakage in the steam supply process.
In one aspect, an embodiment of the present invention provides a nuclear steam supply system, including: the system comprises a primary preheater, a secondary preheater, a feed water heater, a deaerator and a flash evaporator, wherein the primary preheater, the secondary preheater and the feed water heater are respectively provided with a secondary loop inlet, a secondary loop outlet, a tertiary loop inlet and a tertiary loop outlet; the second loop outlet of the first-stage preheater is connected with the condenser, and the third loop inlet of the first-stage preheater is a desalted water inlet; the secondary loop outlet of the secondary preheater is connected with the secondary loop inlet of the primary preheater through a pipeline, a first pressure gauge is connected on a connecting pipeline between the secondary loop outlet of the secondary preheater and the secondary loop inlet of the primary preheater, a deaerator is connected between the three loop outlet of the primary preheater and the three loop inlet of the secondary preheater, and a second pressure gauge and a first control valve are connected on a connecting pipeline between the deaerator and the three loop outlet of the primary preheater; the secondary loop outlet of the feed water heater is connected with the secondary loop inlet of the secondary preheater through a pipeline, the secondary loop inlet of the feed water heater is connected with a high-temperature steam pipeline, a third pressure gauge is connected to the high-temperature steam pipeline, and the tertiary loop inlet of the feed water heater is connected with the tertiary loop outlet of the secondary preheater through a pipeline; the flash evaporator is provided with a water inlet, a water outlet and a steam outlet, the water inlet of the flash evaporator is connected with a three-loop outlet of the feed water heater through a pipeline, a fourth pressure gauge, a radioactivity monitoring instrument and a second control valve are connected on a connecting pipeline between the three-loop outlet of the feed water heater and the water inlet of the flash evaporator, the second control valve is positioned at the downstream position of the fourth pressure gauge and the radioactivity monitoring instrument, and the steam outlet of the flash evaporator is connected with a user end through a pipeline.
According to the invention, the pressure gauge, the control valve and the radioactivity monitoring instrument are arranged in the two-loop pipeline and the three-loop pipeline, so that radioactivity and the pressure difference between the two-loop pipeline and the three-loop pipeline can be monitored on line, and the risk of nuclear leakage in the steam supply process can be avoided.
In some embodiments, the deaerator is provided with a steam inlet, a water inlet and a water outlet, wherein the water inlet of the deaerator is connected with the three-loop outlet of the primary preheater through a pipeline, and the water outlet of the deaerator is connected with the three-loop inlet of the secondary preheater through a pipeline. Oxygen contained in the desalted water is removed, and the purity of the steam is improved.
In some embodiments, the vapor inlet of the deaerator is connected to the vapor outlet of the flash evaporator by a conduit. A portion of the vapor exiting the flash vessel is passed to a deaerator to heat demineralized water.
In some embodiments, the steam inlet of the deaerator is connected to a high temperature steam line. When equipment such as flash evaporator is located industry user local, because the distance between flash evaporator and the deaerator is far away, steam can cool down into water, therefore the flash evaporator can't carry steam to the deaerator in heat demineralized water, and the steam in the deaerator can derive from the high temperature steam of two return circuits.
In some embodiments, the water outlet of the flash evaporator is connected to the three-circuit inlet of the feedwater heater by a conduit. The water which is not flashed into steam in the flash evaporator is converged with the water of the three loops for recycling, so that the waste of resources is avoided.
In some embodiments, the system further comprises a first control unit and a second control unit, wherein the first control unit is respectively and electrically connected with the first pressure gauge, the second pressure gauge and the first control valve, and the second control unit is respectively and electrically connected with the third pressure gauge, the fourth pressure gauge, the radioactivity monitoring instrument and the second control valve. The control unit can automatically control the opening and closing of the control valve according to the data of the pressure gauge and the radioactivity monitoring instrument, so that automation and quick response are realized.
In some embodiments, an electric heater is connected to the connecting line between the three-circuit outlet of the feedwater heater and the water inlet of the flash evaporator, and the electric heater is arranged between the second control valve and the flash evaporator. The water of the three loops can be further heated, and the flash evaporation time is shortened.
In some embodiments, the flash evaporator is connected with a liquid level meter, a pressure boosting pump is connected on a connecting pipeline of a water outlet of the deaerator and a three-loop inlet of the secondary preheater, the deaerator is also provided with a circulating water inlet, a circulating pipeline is connected between an outlet of the pressure boosting pump and the circulating water inlet, a recirculation valve is connected on the circulating pipeline, and the liquid level meter and the recirculation valve are electrically connected to a third control unit together. The third control unit automatically adjusts the valve opening of the recirculation valve according to the liquid level of the flash evaporator so as to achieve the purpose of adjusting the water supplementing amount, for example, when the liquid level of the flash evaporator is higher, the valve opening of the recirculation valve is increased, so that a large amount of water supplementing conveyed by the booster pump passes through the recirculation valve and returns to the deaerator, and the purpose of limiting the liquid level of the flash evaporator to be further increased is achieved, and vice versa.
In some embodiments, a connection pipeline between the steam outlet of the flash evaporator and the user side is connected with a compressor. The steam finally generated by the system is conveyed to a user after the pressure and the temperature of the steam are increased by the compressor, so that the quality of the steam is improved.
Another embodiment of the present invention provides a nuclear steam supply method, using the above nuclear steam supply system, including the following steps: the low-temperature demineralized water sequentially enters a primary preheater, a deaerator, a secondary preheater and a feed water heater to be heated and deaerated to obtain high-temperature demineralized water, meanwhile, high-temperature steam from a nuclear power plant is sequentially introduced into the feed water heater, the secondary preheater and the primary preheater to exchange heat with the low-temperature demineralized water, and the high-temperature steam enters a condenser to recover water after being cooled; the high-temperature desalted water enters a flash evaporator for flash evaporation to obtain steam and water, when the flash evaporator is arranged at the local position of a user side, all the steam discharged from the flash evaporator is conveyed to the user side, and the steam in the deaerator is derived from the high-temperature steam entering a second loop; when the flash evaporator is far away from the local of the user side, one part of steam discharged from the flash evaporator is conveyed to the local of the user side, and the other part of steam is conveyed to the deaerator; monitoring the values of the first pressure gauge, the second pressure gauge, the third pressure gauge, the fourth pressure gauge and the radioactivity monitoring instrument, wherein the value of the first pressure gauge is kept lower than the value of the second pressure gauge, the value of the third pressure gauge is lower than the value of the fourth pressure gauge, and the value of the radioactivity monitoring instrument is kept below a safe value; when the pressure difference between the first pressure gauge and the second pressure gauge is lower than a certain set value, the first control valve is closed; and when the pressure difference between the third pressure gauge and the fourth pressure gauge is lower than a certain set value or the value of the radioactivity monitoring instrument reaches or exceeds a safety value, closing the second control valve.
The invention can monitor radioactivity on line and the pressure difference between the two-loop pipeline and the three-loop pipeline, and can avoid the risk of nuclear leakage in the steam supply process.
Drawings
The foregoing and/or additional aspects and advantages of the present invention will become apparent and may be better understood from the following description of embodiments with reference to the accompanying drawings,
wherein:
FIG. 1 is a schematic diagram of a nuclear steam supply system in accordance with an embodiment of the present invention;
FIG. 2 is a schematic diagram of the structure of a flash evaporator in a nuclear steam supply system according to an embodiment of the present invention when the flash evaporator is located locally to an industrial user;
reference numerals:
1-a condenser; 2-a primary preheater; a 3-secondary preheater; 4-feedwater heater; 5-a third pressure gauge; 6-a fourth pressure gauge; 7-radioactivity monitoring instrument; 8-a second control unit; 9-a second control valve; 10-an electric heater; 11-a second pressure reducing valve; 12-flash vessel; 13-a compressor; 14-a third control valve; 15-a first check valve; a 16-deaerator; 17-level gauge; 18-a third control unit; 19-a recirculation valve; 20-a second check valve; 21-a circulation pump; 22-booster pump; 23-a desalting water pump; 24-a first control unit; 25-a second pressure gauge; 26-a first control valve; 27-a first pressure gauge; 28-a first pressure reducing valve.
Detailed Description
Reference will now be made in detail to embodiments of the present invention, examples of which are illustrated in the accompanying drawings. The embodiments described below by referring to the drawings are illustrative and intended to explain the present invention and should not be construed as limiting the invention.
The nuclear steam supply system and the supply method according to the embodiment of the present invention are described below with reference to the accompanying drawings.
As shown in fig. 1-2, in one aspect, an embodiment of the present invention provides a nuclear steam supply system, including: the primary preheater 2, the secondary preheater 3, the feedwater heater 4, the deaerator 16 and the flash evaporator 12 are provided with a secondary loop inlet, a secondary loop outlet, a tertiary loop inlet and a tertiary loop outlet; the outlet of the second loop of the primary preheater 2 is connected with the condenser 1, and the inlet of the third loop of the primary preheater 2 is a desalted water inlet; the second loop outlet of the second-stage preheater 3 is connected with the second loop inlet of the first-stage preheater 2 through a pipeline, a first pressure gauge 27 is connected on a connecting pipeline between the second loop outlet of the second-stage preheater 3 and the second loop inlet of the first-stage preheater 2, a deaerator 16 is connected between the third loop outlet of the first-stage preheater 2 and the third loop inlet of the second-stage preheater 3, and a second pressure gauge 25 and a first control valve 26 are connected on a connecting pipeline between the deaerator 16 and the third loop outlet of the first-stage preheater 2; the outlet of the secondary loop of the feed water heater 4 is connected with the inlet of the secondary loop of the secondary preheater 3 through a pipeline, the inlet of the secondary loop of the feed water heater 4 is connected with a high-temperature steam pipeline, a third pressure gauge 5 is connected on the high-temperature steam pipeline, and the inlet of the tertiary loop of the feed water heater 4 is connected with the outlet of the tertiary loop of the secondary preheater 3 through a pipeline; the flash evaporator 12 is provided with a water inlet, a water outlet and a steam outlet, the water inlet of the flash evaporator 12 is connected with the three-loop outlet of the feed water heater 4 through a pipeline, a fourth pressure gauge 6, a radioactivity monitoring instrument 7 and a second control valve 9 are connected on a connecting pipeline between the three-loop outlet of the feed water heater 4 and the water inlet of the flash evaporator 12, the second control valve 9 is positioned at the downstream position of the fourth pressure gauge 6 and the radioactivity monitoring instrument 7, and the steam outlet of the flash evaporator 12 is connected with a user end through a pipeline.
According to the invention, the pressure gauge, the control valve and the radioactivity monitoring instrument 7 are arranged in the two-loop pipeline and the three-loop pipeline, so that radioactivity and the pressure difference between the two-loop pipeline and the three-loop pipeline can be monitored on line, and the risk of nuclear leakage in the steam supply process can be avoided.
It will be appreciated that it is desirable to ensure that the pressure in the second circuit is less than the pressure in the third circuit, since the radioactive material in the second circuit is prevented from leaking into the third circuit. Therefore, pressure gauges are needed to be arranged in the two-circuit pipeline and the three-circuit pipeline to monitor the pressure difference between the two circuits and the three circuits, and when the pressure difference is smaller than a safety value, the corresponding control valve is closed in time to prevent radioactive substances in the two circuits from leaking into the three circuits. When the value of the radioactive monitoring meter 7 exceeds the set safety value, the second control valve 9 needs to be closed in time to prevent the radioactive substance which has leaked into the three circuits from being further delivered to the user side. The first control valve 26 forms a double protection with the second control valve 9.
Further, the high-temperature steam pipeline is connected with a pressurized water reactor nuclear power plant steam-water separation reheater, and the pressurized water reactor nuclear power plant steam-water separation reheater conveys high-temperature steam (namely, two-loop steam) into the high-temperature steam pipeline.
Further, the first control valve 26 and the second control valve 9 are isolation valves.
Further, the desalted water introduced into the desalted water inlet of the primary preheater 2 may be desalted water of sea water.
Further, a demineralized water pump 23 is connected to a line connected to the demineralized water inlet of the primary preheater 2.
Further, a first pressure reducing valve 28 is connected to a connecting pipeline between the second loop outlet of the second-stage preheater 3 and the second loop inlet of the first-stage preheater 2, and the first pressure reducing valve 28 is arranged between the first pressure gauge 27 and the second-stage preheater 3. Since condensed water may still have a high pressure after heat exchange with the secondary preheater 3 through the feedwater heater 4, a first pressure reducing valve 28 is required to reduce the pressure of the water.
Further, the number of the radioactivity monitoring meters 7 is not limited to 1, and may be plural kinds of radioactivity monitoring meters 7, for example, inert gas radioactivity monitoring meters 7, N-16 radioactivity monitoring meters 7, tritium monitoring meters, and the like.
Further, the top in the flash evaporator 12 is provided with a steam-water separation device, so that the dryness of steam can be further improved, and the separated water falls into the bottom of the flash evaporator 12. The bottom of the flash evaporator 12 maintains a certain liquid level, ensures that the pressure of the heating flash cycle is maintained stable, and simultaneously ensures that the circulation pump 21 will not cavitation.
Further, the primary preheater 2 is a primary feed water preheater, and the secondary preheater 3 is a secondary feed water preheater.
In some embodiments, deaerator 16 has a steam inlet, a water inlet, and a water outlet, the water inlet of deaerator 16 is connected by piping to the three-circuit outlet of primary preheater 2, and the water outlet of deaerator 16 is connected by piping to the three-circuit inlet of secondary preheater 3. Oxygen contained in the desalted water is removed, and the purity of the steam is improved.
In some embodiments, the vapor inlet of deaerator 16 is connected to the vapor outlet of flash vessel 12 by a conduit. A portion of the vapor exiting flash vessel 12 is passed to deaerator 16 to heat demineralized water.
Further, a first check valve 15 is connected to a connection line between a steam inlet of the deaerator 16 and a steam outlet of the flash evaporator 12.
In some embodiments, as shown in FIG. 2, the steam inlet of deaerator 16 is connected to a high temperature steam line. When the flash evaporator 12 and other devices are located locally in the industrial users, the steam can be cooled into water due to the long distance between the flash evaporator 12 and the deaerator 16, so that the flash evaporator 12 cannot convey the steam into the deaerator 16 to heat the desalted water, and the steam in the deaerator 16 can be derived from the high-temperature steam of the two loops. Pressurized water reactor nuclear power plants only need to deliver high-temperature water to the customer premises (typically an industrial customer premises) where the flashing and use of steam is accomplished locally. The efficiency of transporting high temperature water is higher than that of directly transporting steam.
In some embodiments, the water outlet of the flash evaporator 12 is connected to the three-circuit inlet of the feedwater heater 4 by piping. The water which is not flashed into steam in the flash evaporator 12 is converged with the water of the three loops for recycling, so that the waste of resources is avoided.
Further, a second check valve 20 and a circulation pump 21 are connected to a connection line between the water outlet of the flash evaporator 12 and the three-circuit inlet of the feedwater heater 4. The circulation pump 21 allows moisture not flashed into steam to rapidly enter the feedwater heater 4, and the second check valve 20 prevents water from flowing back into the flasher 12.
In some embodiments, the system further comprises a first control unit 24 and a second control unit 8, wherein the first control unit 24 is electrically connected with the first pressure gauge 27, the second pressure gauge 25 and the first control valve 26 respectively, and the second control unit 8 is electrically connected with the third pressure gauge 5, the fourth pressure gauge 6, the radioactivity monitoring instrument 7 and the second control valve 9 respectively. The control unit can automatically control the opening and closing of the control valve according to the data of the pressure gauge and the radioactivity monitoring instrument 7, so that automation and quick response are realized.
In some embodiments, an electric heater 10 is connected to the connecting line between the three-circuit outlet of the feedwater heater 4 and the water inlet of the flash evaporator 12, and the electric heater 10 is disposed between the second control valve 9 and the flash evaporator 12. The water of the three loops can be further heated, and the flash evaporation time is shortened.
Further, a second pressure reducing valve 11 is connected to the connecting line between the electric heater 10 and the flash evaporator 12, so that the water is reduced in pressure after being heated by the electric heater 10, and then enters the flash evaporator 12.
In some embodiments, the flash evaporator 12 is connected with a liquid level meter 17, a pressure boosting pump 22 is connected on a connecting pipeline between a water outlet of the deaerator 16 and a three-loop inlet of the secondary preheater 3, the deaerator 16 is also provided with a circulating water inlet, a circulating pipeline is connected between an outlet of the pressure boosting pump 22 and the circulating water inlet, a recirculation valve 19 is connected on the circulating pipeline, and the liquid level meter 17 and the recirculation valve 19 are electrically connected to a third control unit 18 together. The third control unit 18 automatically adjusts the valve opening of the recirculation valve 19 according to the liquid level of the flash evaporator 12, so as to achieve the purpose of adjusting the water supplementing amount, for example, when the liquid level of the flash evaporator 12 is higher, the valve opening of the recirculation valve 19 is increased, so that a large amount of water supplementing conveyed by the booster pump 22 passes through the recirculation valve 19 and returns to the deaerator 16, and the purpose of limiting the liquid level of the flash evaporator 12 to further rise is achieved, and vice versa.
In some embodiments, a compressor 13 is connected to a connection line between the steam outlet of the flash evaporator 12 and the user side. The steam finally generated by the system is conveyed to a user after the pressure and the temperature of the steam are increased by the compressor 13, so that the quality of the steam is improved.
Further, a third control valve 14 is connected to a connection pipeline between the compressor 13 and the user terminal, and the third control valve 14 is specifically an isolation valve.
Further, the devices, the components, and the like involved in the present embodiment are not limited to one, and may be provided in plural according to actual needs.
As shown in fig. 1-2, another embodiment of the present invention provides a nuclear steam supply method, using the above-mentioned nuclear steam supply system, comprising the following steps: the low-temperature demineralized water sequentially enters a primary preheater 2, a deaerator 16, a secondary preheater 3 and a feed water heater 4 for heating and deaerating to obtain high-temperature demineralized water, meanwhile, high-temperature steam from a nuclear power plant is sequentially introduced into the feed water heater 4, the secondary preheater 3 and the primary preheater 2 for exchanging heat with the low-temperature demineralized water, most of heat of the secondary steam is released into a three-loop, and the high-temperature steam enters a condenser 1 for water recovery after being cooled; the high-temperature desalted water enters a flash evaporator 12 for flash evaporation to obtain steam and water, when the flash evaporator 12 is arranged at the local position of a user side, all the steam discharged from the flash evaporator 12 is conveyed to the user side, and the steam in a deaerator 16 is derived from the high-temperature steam entering a two-loop; when the flash evaporator 12 is far away from the local site of the user side, one part of the steam discharged from the flash evaporator 12 is delivered to the local site of the user side, and the other part is delivered to the deaerator 16; monitoring the values of the first pressure gauge 27, the second pressure gauge 25, the third pressure gauge 5, the fourth pressure gauge 6 and the radioactivity monitoring instrument 7, keeping the value of the first pressure gauge 27 lower than the value of the second pressure gauge 25, the value of the third pressure gauge 5 lower than the value of the fourth pressure gauge 6, and the value of the radioactivity monitoring instrument 7 below a safe value; when the pressure difference between the first pressure gauge 27 and the second pressure gauge 25 is lower than a certain set value, the first control valve 26 is closed; when the pressure difference between the third pressure gauge 5 and the fourth pressure gauge 6 is lower than a certain set value or the value of the radioactivity monitoring instrument 7 reaches or exceeds a safe value, the second control valve 9 is closed.
The invention can monitor radioactivity on line and the pressure difference between the two-loop pipeline and the three-loop pipeline, and can avoid the risk of nuclear leakage in the steam supply process.
Further, as shown in fig. 2, when the flash evaporator 12 is far from the local site of the user, only a small portion of the steam discharged from the flash evaporator 12 enters the deaerator 16, and the other portion is entirely delivered to the local site of the user. Pressurized water reactor nuclear power plants only need to deliver high-temperature water to the customer premises (typically an industrial customer premises) where the flashing and use of steam is accomplished locally. The efficiency of transporting high temperature water is higher than that of directly transporting steam.
In the description of the present invention, it should be understood that the terms "center", "longitudinal", "lateral", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", "axial", "radial", "circumferential", etc. indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings are merely for convenience in describing the present invention and simplifying the description, and do not indicate or imply that the device or element being referred to must have a specific orientation, be configured and operated in a specific orientation, and therefore should not be construed as limiting the present invention.
Furthermore, the terms "first," "second," and the like, are used for descriptive purposes only and are not to be construed as indicating or implying a relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defining "a first" or "a second" may explicitly or implicitly include at least one such feature. In the description of the present invention, the meaning of "plurality" means at least two, for example, two, three, etc., unless specifically defined otherwise.
In the present invention, unless explicitly specified and limited otherwise, the terms "mounted," "connected," "secured," and the like are to be construed broadly, and may be, for example, fixedly connected, detachably connected, or integrally formed; may be mechanically connected, may be electrically connected or may be in communication with each other; either directly or indirectly, through intermediaries, or both, may be in communication with each other or in interaction with each other, unless expressly defined otherwise. The specific meaning of the above terms in the present invention can be understood by those of ordinary skill in the art according to the specific circumstances.
In the present invention, unless expressly stated or limited otherwise, a first feature "up" or "down" a second feature may be the first and second features in direct contact, or the first and second features in indirect contact via an intervening medium. Moreover, a first feature being "above," "over" and "on" a second feature may be a first feature being directly above or obliquely above the second feature, or simply indicating that the first feature is level higher than the second feature. The first feature being "under", "below" and "beneath" the second feature may be the first feature being directly under or obliquely below the second feature, or simply indicating that the first feature is less level than the second feature.
For purposes of this disclosure, the terms "one embodiment," "some embodiments," "example," "a particular example," or "some examples," etc., mean 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 invention. In this specification, schematic representations of the above terms are not necessarily directed to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Furthermore, the different embodiments or examples described in this specification and the features of the different embodiments or examples may be combined and combined by those skilled in the art without contradiction.
While embodiments of the present invention have been shown and described above, it will be understood that the above embodiments are illustrative and not to be construed as limiting the invention, 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 invention.
Claims (10)
1. A nuclear power vapor supply system, comprising: the system comprises a primary preheater, a secondary preheater, a feed water heater, a deaerator and a flash evaporator, wherein the primary preheater, the secondary preheater and the feed water heater are respectively provided with a secondary loop inlet, a secondary loop outlet, a tertiary loop inlet and a tertiary loop outlet;
the second loop outlet of the first-stage preheater is connected with a condenser, and the third loop inlet of the first-stage preheater is a desalted water inlet;
the secondary pre-heater comprises a primary pre-heater, a secondary pre-heater, a primary pressure gauge, a deaerator, a first control valve, a second pressure gauge, a first control valve and a second control valve, wherein a secondary outlet of the secondary pre-heater is connected with a secondary inlet of the primary pre-heater through a pipeline;
the secondary loop outlet of the feed water heater is connected with the secondary loop inlet of the secondary preheater through a pipeline, the secondary loop inlet of the feed water heater is connected with a high-temperature steam pipeline, a third pressure gauge is connected to the high-temperature steam pipeline, and the tertiary loop inlet of the feed water heater is connected with the tertiary loop outlet of the secondary preheater through a pipeline;
the flash evaporator is provided with a water inlet, a water outlet and a steam outlet, the water inlet of the flash evaporator is connected with the three-loop outlet of the feed water heater through a pipeline, a connecting pipeline between the three-loop outlet of the feed water heater and the water inlet of the flash evaporator is connected with a fourth pressure gauge, a radioactivity monitoring instrument and a second control valve, the second control valve is positioned at the downstream position of the fourth pressure gauge and the radioactivity monitoring instrument, and the steam outlet of the flash evaporator is connected with a user end through a pipeline.
2. The nuclear steam supply system of claim 1, wherein the deaerator has a steam inlet, a water inlet, and a water outlet, the water inlet of the deaerator is connected to the three-circuit outlet of the primary preheater by a conduit, and the water outlet of the deaerator is connected to the three-circuit inlet of the secondary preheater by a conduit.
3. The nuclear power vapor supply system of claim 2, wherein the vapor inlet of the deaerator is connected to the vapor outlet of the flash evaporator by a conduit.
4. The nuclear power vapor supply system of claim 2 wherein a vapor inlet of the deaerator is connected to the high temperature vapor line.
5. The nuclear steam supply system of claim 1, wherein the water outlet of the flash evaporator is connected to the three-circuit inlet of the feedwater heater by a conduit.
6. The nuclear steam supply system of claim 1, further comprising a first control unit electrically connected to the first pressure gauge, the second pressure gauge, the first control valve, respectively, and a second control unit electrically connected to the third pressure gauge, the fourth pressure gauge, the radioactivity monitoring gauge, and the second control valve, respectively.
7. The nuclear steam supply system of claim 1, wherein an electric heater is connected to a connection line between the three-circuit outlet of the feedwater heater and the water inlet of the flash evaporator, the electric heater being disposed between the second control valve and the flash evaporator.
8. The nuclear steam supply system according to claim 2, wherein the flash evaporator is connected with a liquid level meter, a booster pump is connected to a connection pipe between a water outlet of the deaerator and a three-loop inlet of the secondary preheater, the deaerator further has a circulating water inlet, a circulating pipe is connected between an outlet of the booster pump and the circulating water inlet, a recirculation valve is connected to the circulating pipe, and the liquid level meter and the recirculation valve are electrically connected to a third control unit together.
9. The nuclear steam supply system of claim 1, wherein a compressor is connected to a connection line between a steam outlet of the flash evaporator and a user side.
10. A nuclear power steam supply method, characterized by using the nuclear power steam supply system according to any one of claims 1 to 9, comprising the steps of:
the low-temperature demineralized water sequentially enters a primary preheater, a deaerator, a secondary preheater and a feed water heater to be heated and deaerated to obtain high-temperature demineralized water, and meanwhile, high-temperature steam from a nuclear power plant is sequentially introduced into the feed water heater, the secondary preheater and the primary preheater to exchange heat with the low-temperature demineralized water, and the high-temperature steam enters a condenser to recover water after being cooled;
the high-temperature desalted water enters a flash evaporator for flash evaporation to obtain steam and water, when the flash evaporator is arranged at the local position of a user side, all the steam discharged from the flash evaporator is conveyed to the user side, and the steam in the deaerator is derived from the high-temperature steam entering a two-loop; when the flash evaporator is far away from the local of the user side, one part of steam discharged from the flash evaporator is conveyed to the local of the user side, and the other part of steam is conveyed to the deaerator;
monitoring the values of a first pressure gauge, a second pressure gauge, a third pressure gauge, a fourth pressure gauge and a radioactivity monitoring instrument, wherein the value of the first pressure gauge is kept lower than the value of the second pressure gauge, the value of the third pressure gauge is lower than the value of the fourth pressure gauge, and the value of the radioactivity monitoring instrument is lower than a safety value;
when the pressure difference between the first pressure gauge and the second pressure gauge is lower than a certain set value, closing a first control valve; and when the pressure difference between the third pressure gauge and the fourth pressure gauge is lower than a certain set value or the value of the radioactive monitoring instrument reaches or exceeds a safety value, closing the second control valve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311406170.5A CN117346133A (en) | 2023-10-26 | 2023-10-26 | Nuclear energy steam supply system and supply method |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202311406170.5A CN117346133A (en) | 2023-10-26 | 2023-10-26 | Nuclear energy steam supply system and supply method |
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| CN117346133A true CN117346133A (en) | 2024-01-05 |
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| CN202311406170.5A Pending CN117346133A (en) | 2023-10-26 | 2023-10-26 | Nuclear energy steam supply system and supply method |
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| CN (1) | CN117346133A (en) |
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2023
- 2023-10-26 CN CN202311406170.5A patent/CN117346133A/en active Pending
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