CN105957570B - The system and method that one loop of nuclear power station temperature carries out heat examination is lifted using external steam - Google Patents
The system and method that one loop of nuclear power station temperature carries out heat examination is lifted using external steam Download PDFInfo
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- CN105957570B CN105957570B CN201610496470.0A CN201610496470A CN105957570B CN 105957570 B CN105957570 B CN 105957570B CN 201610496470 A CN201610496470 A CN 201610496470A CN 105957570 B CN105957570 B CN 105957570B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
- G21D5/04—Reactor and engine not structurally combined
- G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
- G21D5/12—Liquid working medium vaporised by reactor coolant
- G21D5/14—Liquid working medium vaporised by reactor coolant and also superheated by reactor coolant
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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)
- High Energy & Nuclear Physics (AREA)
- Control Of Turbines (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The present invention is a kind of to lift the system and method that one loop of nuclear power station temperature carries out heat examination using external steam, the system includes feedwater pump discharge isolating door, high-pressure heater shunt valve, evaporator, main inlet throttle-stop valve, external steam and is filled with valve group, pressure vessel and hydrophobic valve, wherein：The outlet of feedwater pump discharge isolating door is connected on the entrance of high-pressure heater shunt valve, and perforate installs external steam and is filled with valve group on the feedwater piping after feedwater pump discharge isolating door；The outlet of pressure vessel is connected on a side entrance of evaporator, and a side outlet of evaporator is connected on the entrance of pressure vessel, and the outlet of high-pressure heater shunt valve is connected on the secondary side entrance of evaporator；The entrance of main inlet throttle-stop valve is connected on the secondary side outlet of evaporator, the live steam piping before main inlet throttle-stop valve and connects hydrophobic valve.The present invention heats primary Ioops using external steam by evaporator so that temperature needed for primary Ioops temperature reaches heat examination in the short period, substantially reduces the heat examination time, reduces the test run duration.
Description
Technical field：
The present invention relates to technical field of nuclear power, and in particular to one kind is entered using external steam lifting one loop of nuclear power station temperature
The system and method for row heat examination.
Background technology：
Current nuclear power station heat examination mainly rotates the frictional heat heating water (helium) produced using nuclear island main pump (main core blower fan)
To lift primary Ioops temperature, due to the thermal Finite produced by main pump (main core blower fan) spin friction, the lifting of primary Ioops temperature compared with
Slowly so that the heat examination time is longer.
The content of the invention：
It is an object of the invention to the limitation that primary Ioops temperature methods are lifted for current nuclear power station heat examination, there is provided one
Plant and lift the system and method that one loop of nuclear power station temperature carries out heat examination using external steam.
To reach above-mentioned purpose, the present invention adopts the following technical scheme that to realize：
The system that one loop of nuclear power station temperature progress heat examination is lifted using external steam, including feedwater pump discharge isolating door,
High-pressure heater shunt valve, evaporator, main inlet throttle-stop valve, external steam are filled with valve group, pressure vessel and hydrophobic valve, wherein：
The outlet of feedwater pump discharge isolating door is connected on the entrance of high-pressure heater shunt valve, after feedwater pump discharge isolating door
Feedwater piping on perforate install external steam be filled with valve group；
The outlet of pressure vessel is connected on the first entrance of evaporator, and the first outlet of evaporator is connected on entering for pressure vessel
Mouthful, the outlet of high-pressure heater shunt valve is connected on the second entrance of evaporator；
Working medium in pressure vessel is driven by the power drive unit in pressure vessel, is come for pressurized-water reactor nuclear power plant
Say, its working medium is demineralized water, and drive device is main pump, for HTGR Nuclear Power Plant, its working medium is helium, driving dress
It is set to Helium fan；Evaporator is shell-and-tube heat exchanger, and shell-side is the primary side of evaporator, and pipe side is the secondary side of evaporator,
The first entrance of evaporator accesses the primary side of evaporator, and the first outlet of evaporator is a side outlet of evaporator, evaporation
The second entrance of device accesses the secondary side entrance of evaporator, and the secondary side outlet of evaporator is connected on the second outlet of evaporator；With
The system that evaporator primary side is connected turns into primary Ioops, and the system being connected with evaporator secondary side turns into secondary circuit；
The entrance of main inlet throttle-stop valve is connected on the second outlet of evaporator, and hydrophobic valve is connect on the live steam piping before main inlet throttle-stop valve.
Of the invention further improve be, external steam be filled with valve group include it is inverse against fill that vapour direction is sequentially connected
Only door, regulation door and cut-off gate.
Further improve of the invention is that hydrophobic valve is included before main inlet throttle-stop valve, two after feedwater pump discharge isolating door
All hydrophobic valves on loop.
The method that one loop of nuclear power station temperature carries out heat examination is lifted using external steam, is comprised the following steps：
1) feedwater pump discharge isolating door, main inlet throttle-stop valve are closed tight, opens hydrophobic valve；
2) by external steam by external steam be filled with valve group be filled with high-pressure heater shunt valve, evaporator it is secondary
Side, until main inlet throttle-stop valve before, it is hydrophobic to be discharged by hydrophobic valve；
3) speed is filled be filled with the regulation gate control steam that is filled with steam course by external steam in valve group,
Ensure that steam is filled with gently, do not occur water slug, and ensure that the temperature rise speed of evaporator is less than its temperature limit；
4) after the steam discharged from hydrophobic valve is without water, hydrophobic valve is closed, subsequent secondary circuit pressure, temperature will be slow
It is slow to rise, in heating, boost process, it is ensured that the heating of evaporator, the rate of rise are less than its temperature, pressure limit；
5) start the drive device in pressure vessel, rotated by drive device and primary Ioops working medium circulation is flowed
Come, primary Ioops working medium absorbs the heat of secondary circuit steam, temperature is slowly raised, meanwhile, drive device frictional heat further adds
The working medium of hot primary Ioops；
6) with the lifting of secondary circuit temperature, primary Ioops temperature is also slowly lifted, when secondary circuit, primary Ioops temperature close to
After external steam temperature, stop being filled with steam to secondary circuit, and close pitch and cut-off gate that external steam is filled with valve group, this
When external steam be filled with the non-return flap of valve group and also close immediately, secondary circuit is in state of isolation；
7) primary Ioops drive device continues to rotate, and the heat that its spin friction is produced further is heated to primary Ioops, until
Primary Ioops temperature meets the requirement of heat examination.
Further improve of the invention is that external steam is starting trouble steam, heating boiler steam or adjacent machine auxiliary
Steam.
Compared with prior art, the present invention has the advantage that：
What the present invention was provided lifts the system and method that one loop of nuclear power station temperature carries out heat examination using external steam.Its
In, the system has following clear advantage：
(1) external steam temperature typically has 200 DEG C or so, using external steam by secondary circuit back heating primary Ioops to connecing
Be bordering on the temperature of external steam, it is only necessary to using main pump (main core blower fan) rotation by primary Ioops working medium from 200 DEG C or so lifting to
The temperature that heat examination needs, can thus greatly reduce the time required for lifting primary Ioops working medium, so that the heat examination time is shortened,
Reduce the nuclear power generating sets test run duration.
(2) for HTGR, during heat examination, secondary circuit is full of nitrogen, now secondary circuit atmosphere with it is normal
The atmosphere difference of operation is larger, and if secondary circuit is vapor, then with actual motion atmosphere than relatively similar, therefore heat examination effect
More preferably；Vapor price for nitrogen is lower, therefore cost is lower；Vapor will not produce asphyxia risk, also more pacify
Entirely.
(3) system mainly make use of the original equipment of nuclear power station, and extra increased equipment is less, and cost of investment is few.
This method and the method used at present have compared following clear advantage：
(1) external steam temperature typically has 200 DEG C or so, using external steam by secondary circuit back heating primary Ioops to connecing
Be bordering on the temperature of external steam, it is only necessary to using main pump (main core blower fan) rotation by primary Ioops working medium from 200 DEG C or so lifting to
The temperature that heat examination needs, can thus greatly reduce the time required for lifting primary Ioops working medium, so that the heat examination time is shortened,
Reduce the nuclear power generating sets test run duration.
(2) for HTGR, during heat examination, secondary circuit is full of nitrogen, now secondary circuit atmosphere with it is normal
The atmosphere difference of operation is larger, and if secondary circuit is vapor, then with actual motion atmosphere than relatively similar, therefore heat examination effect
More preferably；Vapor price for nitrogen is lower, therefore cost is lower；Vapor will not produce asphyxia risk, also more pacify
Entirely.
Brief description of the drawings：
Fig. 1 lifts the structured flowchart that one loop of nuclear power station temperature carries out the system of heat examination for the present invention using external steam.
Embodiment：
The present invention is made further instructions below in conjunction with accompanying drawing.
As shown in figure 1, the system that one loop of nuclear power station temperature progress heat examination is lifted using external steam that the present invention is provided,
Including feedwater pump discharge isolating door 1, high-pressure heater shunt valve 2, evaporator 3, main inlet throttle-stop valve 4, external steam be filled with valve group 5,
Pressure vessel 6 and hydrophobic valve 7, wherein：The outlet of feedwater pump discharge isolating door 1 is connected on the entrance of high-pressure heater shunt valve 2,
Perforate installs external steam and is filled with valve group 5 on feedwater piping after feedwater pump discharge isolating door 1；The outlet of pressure vessel 6
The first entrance of evaporator 3 is connected on, the first outlet of evaporator 3 is connected on the entrance of pressure vessel, high-pressure heater shunt valve 2
Outlet is connected on the second entrance of evaporator 3；Working medium in pressure vessel 6 is driven by the power drive unit in pressure vessel 6,
For pressurized-water reactor nuclear power plant, its working medium is demineralized water, and drive device is main pump, for HTGR Nuclear Power Plant,
Its working medium is helium, and drive device is Helium fan；Evaporator 3 is shell-and-tube heat exchanger, and shell-side is the primary side of evaporator 3,
Pipe side is the secondary side of evaporator 3, and the first entrance of evaporator 3 accesses the primary side of evaporator 3, the first outlet of evaporator 3
For a side outlet of evaporator 3, the second entrance of evaporator 3 accesses the secondary side entrance of evaporator 3, evaporator 3 it is secondary
Side outlet is connected on the second outlet of evaporator 3；The system being connected with evaporator primary side turns into primary Ioops, secondary with evaporator
The system of side connection turns into secondary circuit；The entrance of main inlet throttle-stop valve 4 is connected on the second outlet of evaporator 3, the live steam pipe before main inlet throttle-stop valve 4
Hydrophobic valve 7 is connect on road.
What the present invention was provided lifts the method that one loop of nuclear power station temperature carries out heat examination using external steam, specifically include with
Lower step：
1) feedwater pump discharge isolating door 1, main inlet throttle-stop valve 4 are closed tight, opens hydrophobic valve 7；
2) by external steam by external steam be filled with valve group 5 be filled with high-pressure heater shunt valve 2, evaporator 3 two
Secondary side, until main inlet throttle-stop valve 4 before, it is hydrophobic to be discharged by hydrophobic valve 7；
3) it is filled with speed be filled with the regulation gate control steam that is filled with steam course by external steam in valve group 5
Degree, it is ensured that steam is filled with gently, does not occur water slug, and ensure that the temperature rise speed of evaporator 3 is less than its temperature limit；
4) after the steam discharged from hydrophobic valve 7 is without water, hydrophobic valve 7 is closed, subsequent secondary circuit pressure, temperature will
It is slow to rise, in heating, boost process, it is ensured that the heating of evaporator 3, the rate of rise are less than its temperature, pressure limit；
5) start the drive device in pressure vessel 6, rotated by drive device and primary Ioops working medium circulation is flowed
Come, primary Ioops working medium absorbs the heat of secondary circuit steam, temperature is slowly raised, meanwhile, drive device frictional heat further adds
The working medium of hot primary Ioops；
6) with the lifting of secondary circuit temperature, primary Ioops temperature is also slowly lifted, when secondary circuit, primary Ioops temperature close to
After external steam temperature, stop being filled with steam to secondary circuit, and close pitch and cut-off gate that external steam is filled with valve group 5,
Now external steam is filled with the non-return flap of valve group 5 and also closed immediately, and secondary circuit is in state of isolation；
7) primary Ioops drive device continues to rotate, and the heat that its spin friction is produced further is heated to primary Ioops, until
Primary Ioops temperature meets the requirement of heat examination.
Below exemplified by lifting primary Ioops temperature during certain nuclear power generating sets heat examination, illustrate the specific embodiment party of the invention
Formula.
It is 1.25MPa, 193 DEG C of steam that the available outside vapour source of the unit, which includes 1 to produce 42t/h parameters,
Electric boiler and can to produce 10t/h parameters be 1.25MPa, the coal-burning boiler 5 of 193 DEG C of steam.Total steam production is 92t/h.Should
The power of unit main pump (main core blower fan) is 4500KW.
1) feedwater pump discharge isolating door 1, main inlet throttle-stop valve 4 are closed tight, opens all hydrophobic valves of secondary circuit；
2) by external steam by external steam be filled with valve group 5 be filled with high-pressure heater shunt valve 2, evaporator 3 two
Secondary side, until main inlet throttle-stop valve 4 before, it is hydrophobic to be discharged by secondary circuit hydrophobic valve；
3) it is filled with speed be filled with the regulation gate control steam that is filled with steam course by external steam in valve group 5
Degree, it is ensured that steam is filled with gently, does not occur water slug, and ensure that the temperature rise speed of evaporator 3 is less than its temperature limit；
4) after the steam discharged from hydrophobic valve is without water, hydrophobic valve is closed, subsequent secondary circuit pressure, temperature will be slow
It is slow to rise, in heating, boost process, it is ensured that the heating of evaporator 3, the rate of rise are less than its temperature, pressure limit；
5) start the drive device in pressure vessel 6, rotated by drive device and primary Ioops working medium circulation is flowed
Come, primary Ioops working medium absorbs the heat of secondary circuit steam, temperature is slowly raised, meanwhile, drive device frictional heat further adds
The working medium of hot primary Ioops；
6) with the lifting of secondary circuit temperature, primary Ioops temperature is also slowly lifted, when secondary circuit, primary Ioops temperature close to
After 193 DEG C of external steam temperature, stop being filled with steam to secondary circuit, and close external steam to be filled with the pitch of valve group 5 and cutting
Only door, now external steam be filled with the non-return flap of valve group 5 and also close immediately, secondary circuit is in state of isolation；
7) primary Ioops drive device continues to rotate, and the heat that its spin friction is produced further is heated to primary Ioops, until
Primary Ioops temperature meets the requirement (250 DEG C) of heat examination.
By this method, only need system being heated to 250 DEG C from 193 DEG C using main pump (main core blower fan), and routine side
Rule needs system being heated to 250 DEG C from normal temperature.And for HTGR, because its secondary circuit is steam, more
Close to actual operating mode, more preferably, safer, cost is lower (relative to secondary circuit inflated with nitrogen) for heat examination effect.
Claims (3)
1. lift the system that one loop of nuclear power station temperature carries out heat examination using external steam, it is characterised in that pump out including feedwater
Mouth isolating door (1), high-pressure heater shunt valve (2), evaporator (3), main inlet throttle-stop valve (4), external steam are filled with valve group (5), pressure
Force container (6) and hydrophobic valve (7), wherein：
The outlet of feedwater pump discharge isolating door (1) is connected on the entrance of high-pressure heater shunt valve (2), in feedwater pump discharge isolating door
(1) perforate installs external steam and is filled with valve group (5) on the feedwater piping after；
The outlet of pressure vessel (6) is connected on the first entrance of evaporator (3), and the first outlet of evaporator (3) is connected on pressure vessel
Entrance, the outlet of high-pressure heater shunt valve (2) is connected on the second entrance of evaporator (3)；
Working medium in pressure vessel (6) is driven by the power drive unit in pressure vessel (6), is come for pressurized-water reactor nuclear power plant
Say, its working medium is demineralized water, and drive device is main pump, for HTGR Nuclear Power Plant, its working medium is helium, driving dress
It is set to Helium fan；Evaporator (3) is shell-and-tube heat exchanger, and shell-side is the primary side of evaporator (3), and pipe side is evaporator (3)
Secondary side, the primary side of the first entrance access evaporator (3) of evaporator (3), the first outlet of evaporator (3) is evaporator
(3) a side outlet, evaporator (3) second entrance access evaporator (3) secondary side entrance, evaporator (3) it is secondary
Side outlet is connected on the second outlet of evaporator (3)；The system being connected with evaporator primary side turns into primary Ioops, with evaporator two
The system of secondary side connection turns into secondary circuit；
The entrance of main inlet throttle-stop valve (4) is connected on the second outlet of evaporator (3), and drain valve is connect on the live steam piping before main inlet throttle-stop valve (4)
Door (7)；
External steam, which is filled with valve group (5), to be included against filling the non-return flap, regulation door and cut-off gate that vapour direction is sequentially connected；
Hydrophobic valve (7) is included before main inlet throttle-stop valve (4), all drain valves on secondary circuit after the pump discharge isolating door (1) that feeds water
Door.
2. lift the method that one loop of nuclear power station temperature carries out heat examination using external steam, it is characterised in that this method is based on power
Profit is required to lift the system that one loop of nuclear power station temperature carries out heat examination using external steam described in 1, comprised the following steps：
1) feedwater pump discharge isolating door (1) and main inlet throttle-stop valve (4) are closed tight, opens hydrophobic valve (7)；
2) external steam is filled with valve group (5) by external steam and is filled with high-pressure heater shunt valve (2), evaporator (3)
Secondary side and until main inlet throttle-stop valve (4) before, it is hydrophobic pass through hydrophobic valve (7) discharge；
3) speed is filled be filled with the regulation gate control steam that is filled with steam course by external steam in valve group (5),
Ensure that steam is filled with gently, do not occur water slug, and ensure that the temperature rise speed of evaporator (3) is less than its temperature limit；
4) after the steam discharged from hydrophobic valve (7) is without water, hydrophobic valve (7), subsequent secondary circuit pressure and temperature are closed
To slowly it rise, in heating and boost process, it is ensured that the heating of evaporator (3), the rate of rise are less than its temperature, pressure limit
Value；
5) start the drive device in pressure vessel (6), rotated by drive device and primary Ioops working medium circulation is flowed,
Primary Ioops working medium absorbs the heat of secondary circuit steam, and temperature is slowly raised, meanwhile, drive device frictional heat, further heating
The working medium of primary Ioops；
6) with the lifting of secondary circuit temperature, primary Ioops temperature is also slowly lifted, when secondary circuit and primary Ioops temperature are close to outer
After portion's vapor (steam) temperature, stop being filled with steam to secondary circuit, and close pitch and cut-off gate that external steam is filled with valve group (5),
Now external steam is filled with the non-return flap of valve group (5) and also closed immediately, and secondary circuit is in state of isolation；
7) primary Ioops drive device continues to rotate, and the heat that its spin friction is produced further is heated to primary Ioops, until one time
Road temperature meets the requirement of heat examination.
3. according to claim 2 lift the method that one loop of nuclear power station temperature carries out heat examination using external steam, it is special
Levy and be, external steam is starting trouble steam, heating boiler steam or adjacent machine auxiliary steam.
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| Publication number | Priority date | Publication date | Assignee | Title |
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| RU2806440C1 (en) * | 2022-12-30 | 2023-11-01 | Василий Васильевич Лещенко | Nuclear power plant |
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| 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 |
| CN108278586A (en) * | 2018-03-14 | 2018-07-13 | 西安热工研究院有限公司 | A kind of system and method for HTGR Nuclear Power Plant primary Ioops heating and dehumidification |
| CN111768883A (en) * | 2020-07-21 | 2020-10-13 | 西安热工研究院有限公司 | Heating system and method for primary loop cabin during cold test of high-temperature gas cooled reactor nuclear power station |
| CN112209414B (en) * | 2020-09-01 | 2022-11-11 | 靖西天桂铝业有限公司 | Linkage hot test process before alumina production |
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| CN101916596B (en) * | 2010-07-28 | 2013-05-08 | 中科华核电技术研究院有限公司 | Device and system for vacuum-pumping loop of pressurized water reactor of nuclear power station |
| WO2014028630A1 (en) * | 2012-08-14 | 2014-02-20 | Holtec International, Inc. | Nuclear steam supply system |
| JP5931630B2 (en) * | 2012-07-26 | 2016-06-08 | 三菱重工業株式会社 | Injector system and cooling water supply method to steam generator of pressurized water nuclear plant |
| 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 |
| CN205789136U (en) * | 2016-06-28 | 2016-12-07 | 西安热工研究院有限公司 | Utilize external steam to promote one loop of nuclear power station temperature and carry out the system of heat examination |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| RU2806440C1 (en) * | 2022-12-30 | 2023-11-01 | Василий Васильевич Лещенко | Nuclear power plant |
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