CN108665991A - A kind of system and method for high temperature gas cooled reactor nuclear power generating sets very hot startup - Google Patents
A kind of system and method for high temperature gas cooled reactor nuclear power generating sets very hot startup Download PDFInfo
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- CN108665991A CN108665991A CN201810532146.9A CN201810532146A CN108665991A CN 108665991 A CN108665991 A CN 108665991A CN 201810532146 A CN201810532146 A CN 201810532146A CN 108665991 A CN108665991 A CN 108665991A
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
-
- 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
-
- 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
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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- Physics & Mathematics (AREA)
- 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 kind of system and method for high temperature gas cooled reactor nuclear power generating sets very hot startup, which includes the system that steam turbine, evaporator, primary Ioops system, steam-water separator, high-pressure heater, oxygen-eliminating device, feed pump and 7 groups of valve groups are formed.This method includes following key step：The factor of analysis triggering reactor protection, the protection factor that primary Ioops system circulated helium and secondary circuit evaporator feedwater cycle need not be terminated after reactor protection is acted identifies, the cycle of one, secondary circuit is maintained after reactor protection action；Reactor unit is again started up during, recycling carbonated drink steam-water separator is hydrophobic to improve feed temperature to oxygen-eliminating device；Before steam turbine red switch, the steam that evaporator generates is passed through high-pressure heater further to promote feed temperature.High temperature gas cooled reactor nuclear power generating sets shutdown to the time being again started up was reduced to by 170 hours or more within 3 hours by the present invention, substantially increased the availability of high temperature gas cooled reactor nuclear power generating sets.
Description
Technical field
The invention belongs to technical field of nuclear power, and in particular to a kind of system of high temperature gas cooled reactor nuclear power generating sets very hot startup
And method.
Background technology
High temperature gas cooled reactor nuclear power generating sets at present, after tripping, main core wind turbine stops reactor, and main core wind turbine imports and exports baffle
It closes, the secondary side entrance feed-water valve of evaporator and outlet vapor valve are closed, and primary Ioops cycle and secondary circuit cycle have been interrupted；
Low-pressure heater, oxygen-eliminating device, high-pressure heater vapour source are all interrupted, and water supply can not be heated.
System is primarily present following deficiency at present：
1) it after reactor tripping, even if the short time judges unit tripping reason and eliminates tripping factor, can open immediately
It is dynamic, but design must cool down evaporator and reactor at present, could set up primary Ioops cycle again and secondary circuit follows
Ring, and this process needed for more than 170 a hours, reduced the availability of high temperature gas cooled reactor nuclear power generating sets；
2) cooling required of evaporator is by pressure release, emptying, and process control is complicated, the bad control of cooling rate, evaporator
Weld seam easy tos produce crackle, threatens the safety of evaporator；
3) after evaporator secondary side pressure release emptying, secondary pressure is far below a lateral pressure, and evaporator generates reversed pressure
Power deviates evaporator accidental conditions (normal operation secondary side 14Mpa, primary side 7Mpa, secondary pressure after pressure release emptying
Less than 1Mpa, and primary side force pressure people maintains 7MPa), it is easy to damage evaporator；
4) evaporator easy tos produce water hammer, is unfavorable for the safety of evaporator in using auxiliary steam cooling procedure
Operation；
5) it after evaporator cooling, establishes in cyclic process again, since feed temperature heating vapour source is limited, feed temperature is very
Hardly possible improves, and evaporator primary side temperature is very high (especially at the initial stage for starting main core wind turbine), cause evaporator primary side and
The secondary side temperature difference is very big, is easily damaged evaporator.
Invention content
It is an object of the invention to the deficiencies for current machine set system, provide a kind of high temperature gas cooled reactor nuclear power generating sets pole
The system and method for hot starting, hot start.
In order to achieve the above objectives, the present invention adopts the following technical scheme that realize：
A kind of system of high temperature gas cooled reactor nuclear power generating sets very hot startup, including the first valve group, the second valve group, the 4th
Valve group, the 5th valve group, steam-water separator, evaporator, the 6th valve group and oxygen-eliminating device；Wherein,
The first outlet of evaporator is connected on the entrance of the 5th valve group, and the outlet of the 5th valve group is divided into two strands, first strand
It is connected on the entrance of the second valve group, second strand of entrance for being connected on the first valve group, the outlet of the second valve group is connected on steam-water separation
The entrance of device, the first outlet of steam-water separator are connected on the entrance of the 4th valve group, and the second outlet of steam-water separator is connected on
The entrance of six valve groups, the entrance of the outlet of the 6th valve group in oxygen-eliminating device.
The present invention further improve is, the first valve group, the second valve group, the 4th valve group, the 5th valve group and
6th valve group is made of shut-off valve and regulating valve.
The present invention, which further improves, to be, evaporator is a kind of shell-and-tube heat exchanger, is the secondary side of evaporator in pipe,
Outside pipe and shell constitutes the primary side of evaporator.
The present invention, which further improves, to be, further includes steam turbine, high-pressure heater and third valve group；Wherein,
The outlet of first valve group and the 4th valve group is divided into two strands after converging, first strand of entrance for being connected to steam turbine, and
Two strands of entrances for being connected to third valve group, the outlet of third valve group are connected to the first entrance of high-pressure heater, high-pressure heater
Outlet be connected to the first entrance of evaporator.
The present invention, which further improves, to be, third valve group is made of shut-off valve, regulating valve and non-return valve.
The present invention, which further improves, to be, further includes the 8th valve group and feed pump；Wherein,
The outlet of oxygen-eliminating device is connected to the entrance of feed pump, and the outlet of feed pump is connected to the entrance of the 8th valve group, the 8th valve
The outlet of door group is connected to the second entrance of high-pressure heater.
The present invention, which further improves, to be, the 8th valve group is made of shut-off valve, regulating valve and non-return valve.
The present invention, which further improves, to be, further includes primary Ioops system, the outlet of primary Ioops system is connected on evaporator
Second entrance, the second outlet of evaporator are connected on the entrance of primary Ioops system, and nuclear fuel is housed in primary Ioops system, is filled with band
The helium of pressure, helium can recycle under the driving of Helium fan；Helium absorbs the heat of nuclear fuel release, in evaporator one
Secondary side heat release, the water of heating evaporation device secondary side make it become steam, while helium returns to after the cooling of evaporator primary side
In primary Ioops system.
A kind of method of high temperature gas cooled reactor nuclear power generating sets very hot startup, this method are based on a kind of above-mentioned high temperature gas-cooled core
The system of motor group very hot startup, includes the following steps：
1) factor of analysis triggering reactor protection protection, need not terminate primary Ioops system after reactor protection is acted
The protection factor of circulated helium and secondary circuit evaporator feedwater cycle identifies that these protection factors are known as reactor protection A；
2) the waste heat thermic load after reactor shutdown, referred to as reactor thermic load A are determined；
3) it is determined to maintain the minimum circulated helium flow of primary Ioops system circulated helium, referred to as circulated helium flow A；
4) it calculates under reactor thermic load A, circulated helium flow A operating modes, is able to maintain that reactor, evaporator safety temperature
Spend the evaporator feedwater circular flow of variation, referred to as evaporator feedwater circular flow A；
5) it will be less than evaporator secondary side pressure of pressure 1MPa to 3Mpa in unit rated load and be known as evaporator two
Secondary lateral pressure A；
6) it after reactor protection A actions, opens the second valve group, close the first valve group, primary Ioops system helium is followed
Circulation is adjusted to circulated helium flow A, using the regulating valve in feed pump and the 8th valve group by evaporator feedwater recycle stream
Amount is adjusted to evaporator feedwater circular flow A, is adjusted to evaporator secondary pressure using the regulating valve in the 5th valve group
Evaporator secondary pressure A；
7) regulating valve in the 4th valve group is utilized, the pressure for adjusting steam-water separator is arrived higher than the pressure 1Mpa in oxygen-eliminating device
3Mpa, using the regulating valve of the 6th valve group, the water level for adjusting steam-water separator is normal, and the water in steam-water separator is recycled to
In oxygen-eliminating device, the steam in steam-water separator is recycled to by the 4th valve group, third valve group in high-pressure heater；
8) after system run all right, start reactor as needed, when evaporator outlet steam meets steam turbine red switch
After condition, the first valve group is opened, using the regulating valve control in the first valve group into the quantity of steam of steam turbine, carries out steamer
Machine red switch, set grid-connection, the load with needs, complete the very hot startup of unit.
Compared with the existing technology, the present invention has the advantage that：
A kind of system and method for high temperature gas cooled reactor nuclear power generating sets very hot startup provided by the invention, and usually make at present
System has compared following several respects clear advantage：
1) by high temperature gas cooled reactor nuclear power generating sets shutdown to the time being again started up by be reduced within 170 hours or more 3 hours with
It is interior, substantially increase the availability of high temperature gas cooled reactor nuclear power generating sets；
2) high temperature gas cooled reactor nuclear power generating sets Reactor trip is classified, for the guarantor of one, secondary circuit need not be isolated
Shield maintains the cycle of one, secondary circuit, the operation for reducing the cooling to evaporator, reactor, establishing cycle again to reduce
The thermal shock of evaporator, reactor is conducive to the safety of evaporator and reactor；
3) in startup stage, the steam that evaporator itself generates is heated into water supply by high-pressure heater, by carbonated drink point
For the Recovery of the hot water generated from device to oxygen-eliminating device, these measures greatly improve evaporator feedwater temperature, reduce temperature it is relatively low to
Impact of the water to evaporator, is conducive to the safety of evaporator；
4) it is hydrophobic to have recycled the steam-water separator with heat, there is energy-saving effect；
5) steam before the steam turbine red switch of part has been recycled, there is energy-saving effect.
Description of the drawings
Fig. 1 is a kind of structure diagram of the system of high temperature gas cooled reactor nuclear power generating sets very hot startup of the present invention.
In figure：1- steam turbines, the first valve groups of 2-, the second valve groups of 3-, 4- third valve groups, the 4th valve groups of 5-, 6-
5th valve group, 7- steam-water separators, 8- evaporators, 9- primary Ioops systems, the 6th valve groups of 10-, 11- high-pressure heaters, 12-
Oxygen-eliminating device, the 8th valve groups of 13-, 14- feed pumps.
Specific implementation mode
The present invention is further described in detail below in conjunction with attached drawing.
As shown in Figure 1, a kind of system of high temperature gas cooled reactor nuclear power generating sets very hot startup provided by the invention, including steamer
Machine 1, the first valve group 2, the second valve group 3, third valve group 4, the 4th valve group 5, the 5th valve group 6, steam-water separator 7,
Evaporator 8, primary Ioops system 9, the 6th valve group 10, high-pressure heater 11, oxygen-eliminating device 12, the 8th valve group 13 and feed pump
14。
Wherein, the first outlet of evaporator 8 is connected on the entrance of the 5th valve group 6, and the outlet of the 5th valve group 6 is divided into two
Stock, first strand of entrance for being connected on the second valve group 3, second strand of entrance for being connected on the first valve group 2, the outlet of the second valve group 3
It is connected on the entrance of steam-water separator 7, the first outlet of steam-water separator 7 is connected on the entrance of the 4th valve group 5, steam-water separator 7
Second outlet be connected on the entrance of the 6th valve group 10, the entrance of the outlet of the 6th valve group 10 in oxygen-eliminating device 12；First valve
The outlet of group 2 and the 4th valve group 5 is divided into two strands after converging, and first strand of entrance for being connected to steam turbine 1, second strand is connected to third valve
The entrance of door group 4, the outlet of third valve group 4 are connected to the first entrance of high-pressure heater 11, and the outlet of high-pressure heater 11 connects
To the first entrance of evaporator 8；The outlet of oxygen-eliminating device 12 is connected to the entrance of feed pump 14, and the outlet of feed pump 14 is connected to the 8th valve
The entrance of door group 13, the outlet of the 8th valve group 13 is connected to the second entrance of high-pressure heater 11；The outlet of primary Ioops system 9 connects
In the second entrance of evaporator 8, the second outlet of evaporator 8 is connected on the entrance of primary Ioops system 9, is equipped in primary Ioops system 9
Nuclear fuel is filled with the helium with pressure, and helium can recycle under the driving of Helium fan；Helium absorbs nuclear fuel release
Heat, in 8 primary side heat release of evaporator, the water of 8 secondary side of heating evaporation device makes it become steam, while helium is in evaporator 8
It is returned in primary Ioops system 9 after primary side cooling.
First valve group 2, the second valve group 3, the 4th valve group 5, the 5th valve group 6 and the 6th valve group 10 is
It is made of shut-off valve and regulating valve.Third valve group 4 and the 8th valve group 13 are made of shut-off valve, regulating valve and non-return valve.
The evaporator 8 is a kind of shell-and-tube heat exchanger, is the secondary side of evaporator 8 in pipe, and pipe is outer and shell forms
The primary side of evaporator 8.
A kind of method of high temperature gas cooled reactor nuclear power generating sets very hot startup provided by the invention, includes the following steps：
1) factor of analysis triggering reactor protection protection, need not terminate primary Ioops system after reactor protection is acted
The protection factor of 8 watering cycle of 9 circulated heliums and secondary circuit evaporator identifies, is not needed eventually after claiming reactor protection action
Only the protection factor of 8 watering cycle of 9 circulated helium of primary Ioops system and secondary circuit evaporator is known as reactor protection A；
2) the waste heat thermic load after reactor shutdown, referred to as reactor thermic load A are determined；
3) it is determined to maintain the minimum circulated helium flow of 9 circulated helium of primary Ioops system, referred to as circulated helium flow
A；
4) it calculates under reactor thermic load A, circulated helium flow A operating modes, is able to maintain that reactor, evaporator safety temperature
Spend the 8 watering cycle flow of evaporator of variation, referred to as 8 watering cycle flow A of evaporator；
5) it will be less than 8 secondary side of evaporator pressure of pressure 1MPa to 3Mpa in unit rated load and be known as evaporator 8
Secondary pressure A；
6) it after reactor protection A actions, opens the second valve group 3, close the first valve group 2, by 9 helium of primary Ioops system
Circular flow is adjusted to circulated helium flow A, using the regulating valve in feed pump 14 and the 8th valve group 13 by 8 water supply of evaporator
Circular flow is adjusted to 8 watering cycle flow A of evaporator, using the regulating valve in the 5th valve group 6 by 8 two side pressures of evaporator
Power is adjusted to 8 secondary pressure A of evaporator；
7) regulating valve in the 4th valve group 5 is utilized, the pressure of adjustment steam-water separator 7 is higher than the pressure in oxygen-eliminating device 12
1Mpa to 3Mpa, using the regulating valve of the 6th valve group 10, the water level for adjusting steam-water separator 7 is normal, will be in steam-water separator 7
Water be recycled in oxygen-eliminating device 12, the steam in steam-water separator 7 is recycled by the 4th valve group 5, third valve group 4 supreme
It presses in heater 11；
8) after system run all right, start reactor as needed, rushed when 8 outlet vapor of evaporator meets steam turbine 1
After turning condition, the first valve group 2 is opened, the quantity of steam of steam turbine 1 is entered using the regulating valve control in the first valve group 2, into
1 red switch of row steam turbine, set grid-connection, the load with needs, complete the very hot startup of unit.
Claims (9)
1. a kind of system of high temperature gas cooled reactor nuclear power generating sets very hot startup, which is characterized in that including the first valve group (2),
Two valve groups (3), the 4th valve group (5), the 5th valve group (6), steam-water separator (7), evaporator (8), the 6th valve group
(10) and oxygen-eliminating device (12)；Wherein,
The first outlet of evaporator (8) is connected on the entrance of the 5th valve group (6), and the outlet of the 5th valve group (6) is divided into two strands, and
One is connected on the entrance of the second valve group (3), second strand of entrance for being connected on the first valve group (2), the outlet of the second valve group (3)
It is connected on the entrance of steam-water separator (7), the first outlet of steam-water separator (7) is connected on the entrance of the 4th valve group (5), carbonated drink point
Second outlet from device (7) is connected on the entrance of the 6th valve group (10), and the outlet of the 6th valve group (10) is in oxygen-eliminating device (12)
Entrance.
2. a kind of system of high temperature gas cooled reactor nuclear power generating sets very hot startup according to claim 1, which is characterized in that the
One valve group (2), the second valve group (3), the 4th valve group (5), the 5th valve group (6) and the 6th valve group (10) are by cut-off
Valve and regulating valve composition.
3. a kind of system of high temperature gas cooled reactor nuclear power generating sets very hot startup according to claim 1, it is further characterized in that,
Evaporator (8) is a kind of shell-and-tube heat exchanger, is the secondary side of evaporator (8) in pipe, and pipe is outer and shell constitutes evaporator (8)
Primary side.
4. a kind of system of high temperature gas cooled reactor nuclear power generating sets very hot startup according to claim 1, which is characterized in that also
Including steam turbine (1), high-pressure heater (11) and third valve group (4)；Wherein,
The outlet of first valve group (2) and the 4th valve group (5) is divided into two strands after converging, first strand is connected to entering for steam turbine (1)
Mouthful, second strand of entrance for being connected to third valve group (4), the outlet of third valve group (4) is connected to the first of high-pressure heater (11)
The outlet of entrance, high-pressure heater (11) is connected to the first entrance of evaporator (8).
5. a kind of system of high temperature gas cooled reactor nuclear power generating sets very hot startup according to claim 4, which is characterized in that the
Three valve groups (4) are made of shut-off valve, regulating valve and non-return valve.
6. a kind of system of high temperature gas cooled reactor nuclear power generating sets very hot startup according to claim 4, which is characterized in that also
Including the 8th valve group (13) and feed pump (14)；Wherein,
The outlet of oxygen-eliminating device (12) is connected to the entrance of feed pump (14), and the outlet of feed pump (14) is connected to the 8th valve group (13)
The outlet of entrance, the 8th valve group (13) is connected to the second entrance of high-pressure heater (11).
7. a kind of system of high temperature gas cooled reactor nuclear power generating sets very hot startup according to claim 6, which is characterized in that the
Eight valve groups (13) are made of shut-off valve, regulating valve and non-return valve.
8. a kind of system of high temperature gas cooled reactor nuclear power generating sets very hot startup according to claim 6, which is characterized in that also
Including primary Ioops system (9), the outlet of primary Ioops system (9) is connected on the second entrance of evaporator (8), and the second of evaporator (8)
Outlet is connected on the entrance of primary Ioops system (9), and nuclear fuel is housed in primary Ioops system (9), is filled with the helium with pressure, helium
It can be recycled under the driving of Helium fan；The heat that helium absorbs nuclear fuel release adds in evaporator (8) primary side heat release
The water of hot vaporizer (8) secondary side makes it become steam, while helium returns to one time after the cooling of evaporator (8) primary side
In road system (9).
9. a kind of method of high temperature gas cooled reactor nuclear power generating sets very hot startup, which is characterized in that this method is based on claim 8 institute
A kind of system for the high temperature gas cooled reactor nuclear power generating sets very hot startup stated, includes the following steps：
1) factor of analysis triggering reactor protection protection, need not terminate primary Ioops system (9) after reactor protection is acted
Circulated helium and the protection factor of secondary circuit evaporator (8) watering cycle identify that these protection factors are known as reactor guarantor
Protect A；
2) the waste heat thermic load after reactor shutdown, referred to as reactor thermic load A are determined；
3) it is determined to maintain the minimum circulated helium flow of primary Ioops system (9) circulated helium, referred to as circulated helium flow A；
4) it calculates under reactor thermic load A, circulated helium flow A operating modes, is able to maintain that reactor, evaporator safe temperature become
Evaporator (8) watering cycle flow of change, referred to as evaporator (8) watering cycle flow A；
5) it will be less than evaporator (8) secondary side pressure of pressure 1MPa to 3Mpa in unit rated load and be known as evaporator (8)
Secondary pressure A；
6) it after reactor protection A actions, opens the second valve group (3), close the first valve group (2), by primary Ioops system (9) helium
Gas circular flow is adjusted to circulated helium flow A, will be evaporated using the regulating valve in feed pump (14) and the 8th valve group (13)
Device (8) watering cycle flow is adjusted to evaporator (8) watering cycle flow A, will be steamed using the regulating valve in the 5th valve group (6)
Hair device (8) secondary pressure is adjusted to evaporator (8) secondary pressure A；
7) regulating valve in the 4th valve group (5) is utilized, the pressure of adjustment steam-water separator (7) is higher than the pressure in oxygen-eliminating device (12)
1Mpa to 3Mpa, the water level using the regulating valve of the 6th valve group (10), adjustment steam-water separator (7) is normal, by steam-water separation
Water in device (7) is recycled in oxygen-eliminating device (12), and the steam in steam-water separator (7) is passed through the 4th valve group (5), third valve
Door group (4) is recycled in high-pressure heater (11)；
8) after system run all right, start reactor as needed, when evaporator (8) outlet vapor meets steam turbine (1) punching
After turning condition, the first valve group (2) is opened, the steam of steam turbine (1) is entered using the regulating valve control in the first valve group (2)
Amount carries out steam turbine (1) red switch, set grid-connection, with the load needed, completes the very hot startup of unit.
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| CN201810532146.9A CN108665991B (en) | 2018-05-29 | 2018-05-29 | System and method for starting nuclear power unit of high-temperature gas cooled reactor in polar hot state |
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| CN201810532146.9A CN108665991B (en) | 2018-05-29 | 2018-05-29 | System and method for starting nuclear power unit of high-temperature gas cooled reactor in polar hot state |
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| CN110131003A (en) * | 2019-06-10 | 2019-08-16 | 西安热工研究院有限公司 | A kind of system and method for high temperature gas cooled reactor nuclear power unit secondary circuit start and stop |
| CN113431638A (en) * | 2021-06-21 | 2021-09-24 | 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 |
| CN113944924A (en) * | 2021-10-18 | 2022-01-18 | 西安热工研究院有限公司 | Automatic control system and method for steam temperature at outlet of evaporator of high-temperature gas cooled reactor unit |
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