CN108665991B - System and method for starting nuclear power unit of high-temperature gas cooled reactor in polar hot state - Google Patents
System and method for starting nuclear power unit of high-temperature gas cooled reactor in polar hot state Download PDFInfo
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- CN108665991B CN108665991B CN201810532146.9A CN201810532146A CN108665991B CN 108665991 B CN108665991 B CN 108665991B CN 201810532146 A CN201810532146 A CN 201810532146A CN 108665991 B CN108665991 B CN 108665991B
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- 238000000034 method Methods 0.000 title claims abstract description 20
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 79
- 239000001307 helium Substances 0.000 claims abstract description 38
- 229910052734 helium Inorganic materials 0.000 claims abstract description 38
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims abstract description 38
- 239000007789 gas Substances 0.000 claims abstract description 23
- 230000001105 regulatory effect Effects 0.000 claims description 23
- 238000011010 flushing procedure Methods 0.000 claims description 6
- 239000003758 nuclear fuel Substances 0.000 claims description 6
- 238000001816 cooling Methods 0.000 description 6
- 230000009286 beneficial effect Effects 0.000 description 2
- 230000007547 defect Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000004064 recycling Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000004886 process control Methods 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
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- 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
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
- G21D3/18—Regulation of any parameters in the plant by adjustment of plant external to the reactor only in response to change in reactivity
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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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- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Engine Equipment That Uses Special Cycles (AREA)
Abstract
The invention discloses a system and a method for the hot start of a nuclear power unit of a high-temperature gas cooled reactor, wherein the system comprises a steam turbine, an evaporator, a loop system, a steam-water separator, a high-pressure heater, a deaerator, a water supply pump and 7 groups of valve groups. The method comprises the following main steps: analyzing factors triggering the reactor protection, identifying the protection factors which do not need to terminate the helium circulation of the primary loop system and the water supply circulation of the secondary loop evaporator after the reactor protection action, and maintaining the circulation of the primary loop and the secondary loop after the reactor protection action; in the restarting process of the reactor unit, recovering the steam-water separator to drain water to the deaerator to increase the water supply temperature; before the turbine rotates, the steam generated by the evaporator is led into a high-pressure heater to further raise the temperature of the water supply. According to the invention, the time from the shutdown to the restarting of the high-temperature gas cooled reactor nuclear power unit is shortened from more than 170 hours to less than 3 hours, and the availability of the high-temperature gas cooled reactor nuclear power unit is greatly improved.
Description
Technical Field
The invention belongs to the technical field of nuclear power, and particularly relates to a system and a method for starting a nuclear power unit of a high-temperature gas cooled reactor in a polar hot state.
Background
At present, after a reactor trips, a main nuclear fan stops, an inlet baffle of the main nuclear fan is closed, a water supply valve and an outlet steam valve of a secondary side inlet of an evaporator are closed, and primary loop circulation and secondary loop circulation are interrupted; the low-pressure heater, the deaerator and the high-pressure heater are all interrupted, and the water supply can not be heated.
The prior system mainly has the following defects:
1) After the reactor trips, even if the unit tripping reason is judged in a short time and tripping factors are eliminated, the unit can be started immediately, but the evaporator and the reactor are required to be cooled in the current design, so that primary loop circulation and secondary loop circulation can be built again, and the process requires more than 170 hours, so that the availability of the high-temperature gas cooled reactor nuclear power unit is reduced;
2) The cooling of the evaporator needs pressure relief and evacuation, the process control is complex, the cooling speed is not well controlled, the welding seam of the evaporator is easy to crack, and the safety of the evaporator is threatened;
3) After the pressure of the secondary side of the evaporator is relieved and emptied, the secondary side pressure is far lower than the primary side pressure, the evaporator generates reverse pressure, the normal operation working condition of the evaporator is deviated (14 Mpa of the secondary side is normally operated, 7Mpa of the primary side is ensured, the secondary side pressure is lower than 1Mpa after the pressure relief and the emptying, and the primary side pressure is maintained at 7 Mpa), so that the evaporator is easy to be damaged;
4) In the process of cooling by using auxiliary steam, the evaporator is easy to generate water hammer phenomenon, which is not beneficial to the safe operation of the evaporator;
5) After the evaporator is cooled, in the process of re-establishing circulation, the temperature of the water supply is difficult to increase due to the limited heating steam source of the temperature of the water supply, and the temperature of the primary side of the evaporator is very high (especially in the initial stage of starting the main nuclear fan), so that the temperature difference between the primary side and the secondary side of the evaporator is very large, and the evaporator is easy to damage.
Disclosure of Invention
The invention aims to provide a system and a method for the polar hot start of a high-temperature gas cooled reactor nuclear power unit, aiming at the defects of the conventional unit system.
In order to achieve the above purpose, the invention is realized by adopting the following technical scheme:
a system for the extremely hot start of a high-temperature gas cooled reactor nuclear power unit comprises a first valve group, a second valve group, a fourth valve group, a fifth valve group, a steam-water separator, an evaporator, a sixth valve group and a deaerator; wherein,,
the first outlet of the evaporator is connected with the inlet of the fifth valve group, the outlet of the fifth valve group is divided into two strands, the first strand is connected with the inlet of the second valve group, the second strand is connected with the inlet of the first valve group, the outlet of the second valve group is connected with the inlet of the steam-water separator, the first outlet of the steam-water separator is connected with the inlet of the fourth valve group, the second outlet of the steam-water separator is connected with the inlet of the sixth valve group, and the outlet of the sixth valve group is connected with the inlet of the deaerator.
The invention is further improved in that the first valve group, the second valve group, the fourth valve group, the fifth valve group and the sixth valve group are composed of stop valves and regulating valves.
The invention is further improved in that the evaporator is a shell-and-tube heat exchanger, the secondary side of the evaporator is arranged in the tube, and the tube outer and the shell form the primary side of the evaporator.
The invention is further improved in that the invention also comprises a steam turbine, a high-pressure heater and a third valve group; wherein,,
the outlets of the first valve group and the fourth valve group are merged and then divided into two streams, the first stream is connected to the inlet of the steam turbine, the second stream is connected to the inlet of the third valve group, the outlet of the third valve group is connected to the first inlet of the high-pressure heater, and the outlet of the high-pressure heater is connected to the first inlet of the evaporator.
The invention is further improved in that the third valve group consists of a stop valve, a regulating valve and a non-return valve.
The invention is further improved in that the invention also comprises an eighth valve group and a water supply pump; wherein,,
the outlet of the deaerator is connected to the inlet of the feed water pump, the outlet of the feed water pump is connected to the inlet of the eighth valve group, and the outlet of the eighth valve group is connected to the second inlet of the high-pressure heater.
The invention is further improved in that the eighth valve group consists of a stop valve, a regulating valve and a non-return valve.
The invention further improves the device and the method by further comprising a loop system, wherein an outlet of the loop system is connected with a second inlet of the evaporator, the second outlet of the evaporator is connected with an inlet of the loop system, nuclear fuel is filled in the loop system, helium with pressure is filled in the loop system, and the helium can circulate under the drive of the main helium fan; the helium absorbs heat released by the nuclear fuel, releases heat at the primary side of the evaporator, heats the water at the secondary side of the evaporator to become steam, and returns the helium to the primary side of the evaporator after cooling.
The method for starting the nuclear power unit of the high-temperature gas cooled reactor in the polar hot state is based on the system for starting the nuclear power unit of the high-temperature gas cooled reactor in the polar hot state, and comprises the following steps:
1) Analyzing factors triggering reactor protection, and identifying protection factors which do not need to terminate the helium circulation of the primary loop system and the water supply circulation of the secondary loop evaporator after the reactor protection action, wherein the protection factors are called reactor protection A;
2) Determining the residual heat load after reactor shutdown, namely a reactor heat load A;
3) Determining a minimum helium circulation flow capable of maintaining a loop system helium circulation, called helium circulation flow A;
4) Calculating the water supply circulation flow of the evaporator, namely the water supply circulation flow A of the evaporator, which can maintain the safe temperature change of the reactor and the evaporator under the working conditions of the heat load A and the helium circulation flow A of the reactor;
5) The pressure 1MPa to 3MPa lower than the pressure of the secondary side of the evaporator at the rated load of the unit is called the secondary side pressure A of the evaporator;
6) After the reactor protection A acts, a second valve group is opened, a first valve group is closed, the helium circulation flow of a loop system is adjusted to be helium circulation flow A, the water supply circulation flow of the evaporator is adjusted to be the water supply circulation flow A of the evaporator by utilizing a water supply pump and a regulating valve in an eighth valve group, and the secondary side pressure of the evaporator is adjusted to be the secondary side pressure A of the evaporator by utilizing a regulating valve in a fifth valve group;
7) Adjusting the pressure of the steam-water separator to be 1Mpa to 3Mpa higher than the pressure in the deaerator by using a regulating valve in the fourth valve group, adjusting the water level of the steam-water separator to be normal by using a regulating valve of the sixth valve group, recycling the water in the steam-water separator to the deaerator, and recycling the steam in the steam-water separator to the high-pressure heater through the fourth valve group and the third valve group;
8) When the system is stable in operation, the reactor is started according to the requirement, when the steam at the outlet of the evaporator meets the turbine flushing condition, the first valve group is opened, the steam quantity entering the turbine is controlled by the regulating valve in the first valve group, the turbine flushing, the unit grid connection and the load with the requirement are carried out, and the extremely hot start of the unit is completed.
Compared with the prior art, the invention has the following advantages:
compared with the system commonly used at present, the system and the method for starting the nuclear power unit of the high-temperature gas cooled reactor in the extremely hot state have the following obvious advantages:
1) The time from the shutdown of the high-temperature gas cooled reactor nuclear power unit to the restarting is shortened from more than 170 hours to less than 3 hours, so that the availability of the high-temperature gas cooled reactor nuclear power unit is greatly improved;
2) The shutdown protection of the high-temperature gas cooled reactor nuclear power unit is graded, the protection of a first loop and a second loop is not needed to be isolated, the circulation of the first loop and the second loop is maintained, the operations of cooling an evaporator and a reactor and establishing the circulation again are reduced, the cold and hot impact of the evaporator and the reactor is reduced, and the safety of the evaporator and the reactor is facilitated;
3) In the starting stage, steam generated by the evaporator is heated by a high-pressure heater, hot water generated by the steam-water separator is recovered to the deaerator, the measures greatly improve the temperature of the water fed by the evaporator, reduce the impact of the water fed at a lower temperature on the evaporator, and are beneficial to the safety of the evaporator;
4) The steam-water separator with heat is recovered to drain water, so that the energy-saving effect is achieved;
5) And part of steam before the turbine is turned, so that the energy-saving effect is achieved.
Drawings
FIG. 1 is a block diagram of a system for hot start of a high temperature gas cooled nuclear power unit according to the present invention.
In the figure: 1-steam turbine, 2-first valve group, 3-second valve group, 4-third valve group, 5-fourth valve group, 6-fifth valve group, 7-steam-water separator, 8-evaporator, 9-loop system, 10-sixth valve group, 11-high pressure heater, 12-deaerator, 13-eighth valve group and 14-feed pump.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings.
As shown in fig. 1, the system for the hot start of the nuclear power unit of the high-temperature gas cooled reactor provided by the invention comprises a steam turbine 1, a first valve group 2, a second valve group 3, a third valve group 4, a fourth valve group 5, a fifth valve group 6, a steam-water separator 7, an evaporator 8, a loop system 9, a sixth valve group 10, a high-pressure heater 11, a deaerator 12, an eighth valve group 13 and a water supply pump 14.
The first outlet of the evaporator 8 is connected to the inlet of the fifth valve group 6, the outlet of the fifth valve group 6 is divided into two strands, the first strand is connected to the inlet of the second valve group 3, the second strand is connected to the inlet of the first valve group 2, the outlet of the second valve group 3 is connected to the inlet of the steam-water separator 7, the first outlet of the steam-water separator 7 is connected to the inlet of the fourth valve group 5, the second outlet of the steam-water separator 7 is connected to the inlet of the sixth valve group 10, and the outlet of the sixth valve group 10 is connected to the inlet of the deaerator 12; the outlets of the first valve group 2 and the fourth valve group 5 are merged and then split into two flows, wherein the first flow is connected to the inlet of the steam turbine 1, the second flow is connected to the inlet of the third valve group 4, the outlet of the third valve group 4 is connected to the first inlet of the high-pressure heater 11, and the outlet of the high-pressure heater 11 is connected to the first inlet of the evaporator 8; the outlet of the deaerator 12 is connected to the inlet of the water feed pump 14, the outlet of the water feed pump 14 is connected to the inlet of the eighth valve set 13, and the outlet of the eighth valve set 13 is connected to the second inlet of the high-pressure heater 11; the outlet of a loop system 9 is connected with the second inlet of the evaporator 8, the second outlet of the evaporator 8 is connected with the inlet of the loop system 9, the loop system 9 is filled with nuclear fuel and filled with helium with pressure, and the helium can circulate under the drive of a main helium fan; the helium absorbs heat released by the nuclear fuel, releases heat at the primary side of the evaporator 8, heats the water at the secondary side of the evaporator 8 to become steam, and returns the helium to the primary side of the evaporator 8 after cooling.
The first valve group 2, the second valve group 3, the fourth valve group 5, the fifth valve group 6 and the sixth valve group 10 are composed of stop valves and regulating valves. The third valve group 4 and the eighth valve group 13 are each composed of a stop valve, a regulating valve and a check valve.
The evaporator 8 is a shell-and-tube heat exchanger, the secondary side of the evaporator 8 is arranged in a tube, and the primary side of the evaporator 8 is formed by the outer tube and the shell.
The invention provides a method for starting a nuclear power unit of a high-temperature gas cooled reactor in an extremely hot state, which comprises the following steps:
1) Analyzing factors triggering the protection of the reactor, and identifying the protection factors which do not need to terminate the helium circulation of the primary loop system 9 and the water supply circulation of the secondary loop evaporator 8 after the protection action of the reactor, wherein the protection factors which do not need to terminate the helium circulation of the primary loop system 9 and the water supply circulation of the secondary loop evaporator 8 after the protection action of the reactor are called as reactor protection A;
2) Determining the residual heat load after reactor shutdown, namely a reactor heat load A;
3) Determining a minimum helium circulation flow capable of maintaining a helium circulation of the primary circuit system 9, called helium circulation flow a;
4) Calculating the water supply circulation flow of the evaporator 8, namely the water supply circulation flow A of the evaporator 8, which can maintain the safe temperature change of the reactor and the evaporator under the working conditions of the reactor heat load A and the helium circulation flow A;
5) The pressure 1MPa to 3MPa lower than the pressure of the secondary side of the evaporator 8 at the rated load of the unit is called the secondary side pressure A of the evaporator 8;
6) After the reactor protection A acts, the second valve group 3 is opened, the first valve group 2 is closed, the helium circulation flow of the primary loop system 9 is adjusted to be helium circulation flow A, the water supply circulation flow of the evaporator 8 is adjusted to be the water supply circulation flow A of the evaporator 8 by using the regulating valves in the water supply pump 14 and the eighth valve group 13, and the secondary side pressure of the evaporator 8 is adjusted to be the secondary side pressure A of the evaporator 8 by using the regulating valve in the fifth valve group 6;
7) The regulating valve in the fourth valve group 5 is utilized to regulate the pressure of the steam-water separator 7 to be 1Mpa to 3Mpa higher than the pressure in the deaerator 12, the regulating valve in the sixth valve group 10 is utilized to regulate the water level of the steam-water separator 7 to be normal, the water in the steam-water separator 7 is recycled to the deaerator 12, and the steam in the steam-water separator 7 is recycled to the high-pressure heater 11 through the fourth valve group 5 and the third valve group 4;
8) When the system is stable in operation, the reactor is started according to the requirement, when the steam at the outlet of the evaporator 8 meets the flushing condition of the steam turbine 1, the first valve group 2 is opened, the steam quantity entering the steam turbine 1 is controlled by the regulating valve in the first valve group 2, the flushing of the steam turbine 1, the grid connection of the unit and the load with the requirement are carried out, and the extremely hot start of the unit is completed.
Claims (5)
1. The method is characterized by being based on a system for the hot start of a high-temperature gas cooled reactor nuclear power unit, and the system comprises a first valve group (2), a second valve group (3), a fourth valve group (5), a fifth valve group (6), a steam-water separator (7), an evaporator (8), a sixth valve group (10), a deaerator (12), a steam turbine (1), a high-pressure heater (11), a third valve group (4), a loop system (9), an eighth valve group (13) and a feed pump (14); wherein,,
the first outlet of the evaporator (8) is connected with the inlet of the fifth valve group (6), the outlet of the fifth valve group (6) is divided into two strands, the first strand is connected with the inlet of the second valve group (3), the second strand is connected with the inlet of the first valve group (2), the outlet of the second valve group (3) is connected with the inlet of the steam-water separator (7), the first outlet of the steam-water separator (7) is connected with the inlet of the fourth valve group (5), the second outlet of the steam-water separator (7) is connected with the inlet of the sixth valve group (10), and the outlet of the sixth valve group (10) is connected with the inlet of the deaerator (12);
the outlets of the first valve group (2) and the fourth valve group (5) are merged and then divided into two branches, the first branch is connected to the inlet of the steam turbine (1), the second branch is connected to the inlet of the third valve group (4), the outlet of the third valve group (4) is connected to the first inlet of the high-pressure heater (11), and the outlet of the high-pressure heater (11) is connected to the first inlet of the evaporator (8);
the outlet of the deaerator (12) is connected to the inlet of the water feeding pump (14), the outlet of the water feeding pump (14) is connected to the inlet of the eighth valve group (13), and the outlet of the eighth valve group (13) is connected to the second inlet of the high-pressure heater (11);
the outlet of the loop system (9) is connected with the second inlet of the evaporator (8), the second outlet of the evaporator (8) is connected with the inlet of the loop system (9), nuclear fuel is filled in the loop system (9), helium with pressure is filled in the loop system (9), and the helium can circulate under the driving of the main helium fan; the helium absorbs heat released by the nuclear fuel, releases heat on the primary side of the evaporator (8), heats water on the secondary side of the evaporator (8) to be changed into steam, and returns the helium to a loop system (9) after being cooled on the primary side of the evaporator (8);
the method comprises the following steps:
1) Analyzing factors triggering reactor protection, and identifying protection factors which do not need to terminate the helium circulation of the primary loop system (9) and the water supply circulation of the secondary loop evaporator (8) after the reactor protection action, wherein the protection factors are called reactor protection A;
2) Determining the residual heat load after reactor shutdown, namely a reactor heat load A;
3) Determining a minimum helium circulation flow capable of maintaining a loop system (9) helium circulation, called helium circulation flow a;
4) Under the working conditions of the reactor thermal load A and the helium gas circulation flow A, the water supply circulation flow of the evaporator (8) which can maintain the safe temperature change of the reactor and the evaporator is calculated and is called the water supply circulation flow A of the evaporator (8);
5) The pressure which is lower than the pressure of 1MPa to 3MPa of the secondary side of the evaporator (8) at the rated load of the unit is called the secondary side pressure A of the evaporator (8);
6) After the reactor protection A acts, a second valve group (3) is opened, a first valve group (2) is closed, the helium circulation flow of a primary loop system (9) is adjusted to be helium circulation flow A, the water supply circulation flow of the evaporator (8) is adjusted to be the water supply circulation flow A of the evaporator (8) by utilizing the regulating valves in a water supply pump (14) and an eighth valve group (13), and the secondary side pressure of the evaporator (8) is adjusted to be the secondary side pressure A of the evaporator (8) by utilizing the regulating valve in a fifth valve group (6);
7) The pressure of the steam-water separator (7) is adjusted to be 1Mpa to 3Mpa higher than the pressure in the deaerator (12) by utilizing a regulating valve in the fourth valve group (5), the water level of the steam-water separator (7) is adjusted to be normal by utilizing a regulating valve of the sixth valve group (10), water in the steam-water separator (7) is recovered to the deaerator (12), and steam in the steam-water separator (7) is recovered to the high-pressure heater (11) through the fourth valve group (5) and the third valve group (4);
8) When the system is stable in operation, the reactor is started according to the requirement, and when the steam at the outlet of the evaporator (8) meets the flushing condition of the steam turbine (1), the first valve group (2) is opened, the steam quantity entering the steam turbine (1) is controlled by the regulating valve in the first valve group (2), so that the flushing of the steam turbine (1), the grid connection of the unit and the load with the requirement are carried out, and the extremely hot start of the unit is completed.
2. The method for the extremely hot start-up of the high-temperature gas cooled reactor nuclear power unit according to claim 1, wherein the first valve group (2), the second valve group (3), the fourth valve group (5), the fifth valve group (6) and the sixth valve group (10) are composed of stop valves and regulating valves.
3. The method for hot start-up of a high temperature gas cooled nuclear power plant as recited in claim 1 further characterized in that the evaporator (8) is a shell and tube heat exchanger, the inside of the tube being the secondary side of the evaporator (8), the outside of the tube and the housing forming the primary side of the evaporator (8).
4. The method for the extremely hot start-up of a high temperature gas cooled reactor nuclear power unit according to claim 1, characterized in that the third valve group (4) consists of a shut-off valve, a regulating valve and a non-return valve.
5. A method for the extremely hot start-up of a high temperature gas cooled reactor nuclear power plant according to claim 1, characterized in that the eighth valve group (13) consists of a shut-off valve, a regulating valve and a non-return valve.
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| CN109767852B (en) * | 2019-02-22 | 2024-06-04 | 西安热工研究院有限公司 | Two-loop safety system for reactor emergency shutdown and working method thereof |
| CN110131003B (en) * | 2019-06-10 | 2023-06-27 | 西安热工研究院有限公司 | System and method for starting and stopping two loops of high-temperature gas cooled reactor nuclear power unit |
| CN112768100A (en) * | 2021-02-07 | 2021-05-07 | 西安热工研究院有限公司 | Intermediate steam-water separation direct-current steam generation system and method |
| CN113431638B (en) * | 2021-06-21 | 2022-09-27 | 华能山东石岛湾核电有限公司 | High-temperature gas cooled reactor shaft seal system and rapid gas supply device and method thereof |
| CN113944924B (en) * | 2021-10-18 | 2023-08-22 | 西安热工研究院有限公司 | Automatic control system and method for outlet steam temperature of evaporator of high-temperature gas cooled reactor unit |
| CN114203316B (en) * | 2021-11-08 | 2022-10-21 | 华能核能技术研究院有限公司 | Method and system for measuring reactor power under non-thermal balance working condition of high-temperature gas cooled reactor |
| CN114459013B (en) * | 2022-01-27 | 2023-09-08 | 华能山东石岛湾核电有限公司 | Protection system and method for high-temperature gas cooled reactor steam generator |
| CN114758800B (en) * | 2022-05-17 | 2023-05-12 | 华能山东石岛湾核电有限公司 | Method and system for cooling reactor core after emergency shutdown of high-temperature gas cooled reactor |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106678770A (en) * | 2017-02-27 | 2017-05-17 | 西安热工研究院有限公司 | System and method for heating feed water of evaporator of nuclear power unit |
Family Cites Families (13)
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| JPH0756368B2 (en) * | 1985-12-03 | 1995-06-14 | 株式会社日立製作所 | Steam generator plant |
| JP3085785B2 (en) * | 1992-05-28 | 2000-09-11 | 三菱重工業株式会社 | Boiler feedwater heating device |
| JPH09303113A (en) * | 1996-05-10 | 1997-11-25 | Toshiba Corp | Combined cycle generating plant |
| JP2001324594A (en) * | 2000-05-12 | 2001-11-22 | Toshiba Corp | Nuclear turbine system |
| US7614233B2 (en) * | 2005-01-28 | 2009-11-10 | Hitachi-Ge Nuclear Energy, Ltd. | Operation method of nuclear power plant |
| CN201894889U (en) * | 2010-11-18 | 2011-07-13 | 哈尔滨锅炉厂有限责任公司 | Steam-water separator |
| CN203744209U (en) * | 2013-12-27 | 2014-07-30 | 冯伟忠 | Energy-saving quick-start system applied to thermal power plant |
| CN104296121A (en) * | 2014-09-25 | 2015-01-21 | 黑龙江宏宇电站设备有限公司 | Power station boiler neighbor machine steam heating starting device and warm starting method |
| CN104713074B (en) * | 2015-03-25 | 2016-11-16 | 西安热工研究院有限公司 | A kind of direct current cooker starts the hydrophobic System and method for utilizing pressure flash vessel to reclaim |
| CN105605551B (en) * | 2016-03-14 | 2017-08-25 | 西安热工研究院有限公司 | A kind of system and method for utilization turbine by-pass steam heating pot stove feedwater |
| CN106981322B (en) * | 2017-04-26 | 2018-10-23 | 西安热工研究院有限公司 | A kind of system and method for verifying high temperature gas cooled reactor start and stop heaping equipment function |
| CN107939462B (en) * | 2017-12-21 | 2020-02-18 | 中国能源建设集团广东省电力设计研究院有限公司 | Start-stop system and control method thereof, and secondary loop steam-water system and operation method of nuclear power station |
| CN208189227U (en) * | 2018-05-29 | 2018-12-04 | 西安热工研究院有限公司 | A kind of system of high temperature gas cooled reactor nuclear power unit very hot startup |
-
2018
- 2018-05-29 CN CN201810532146.9A patent/CN108665991B/en active Active
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106678770A (en) * | 2017-02-27 | 2017-05-17 | 西安热工研究院有限公司 | System and method for heating feed water of evaporator of nuclear power unit |
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