CN105957570A - System and method for carrying out hot test by utilizing external steam to raise temperature of primary circuit of nuclear power plant - Google Patents
System and method for carrying out hot test by utilizing external steam to raise temperature of primary circuit of nuclear power plant Download PDFInfo
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- CN105957570A CN105957570A CN201610496470.0A CN201610496470A CN105957570A CN 105957570 A CN105957570 A CN 105957570A CN 201610496470 A CN201610496470 A CN 201610496470A CN 105957570 A CN105957570 A CN 105957570A
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- vaporizer
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- temperature
- external steam
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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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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Control Of Turbines (AREA)
Abstract
The system comprises a system and a method for carrying out hot tests by utilizing external steam to raise temperature of a primary circuit of a nuclear power plant. The system comprises a water supply pump outlet isolation gate, a high-pressure heater bypass pipe, an evaporator, a main throttle valve, an external steam charging valve group, a pressure vessel and a trap valve, wherein an outlet of the water supply pump outlet isolation gate is connected to an inlet of the high-pressure heater bypass pipe, a hole is formed in a water supply pipeline behind the water supply pump outlet isolation gate and is used for installing the external steam charging valve group; an outlet of the pressure vessel is connected to a primary side inlet of the evaporator, a primary side outlet of the evaporator is connected to an inlet of the pressure vessel, and an outlet of the high-pressure heater bypass pipe is connected to a secondary side inlet of the evaporator; and an inlet of the main throttle valve is connected to a secondary side outlet of the evaporator, and a main steam pipeline in front of the main throttle valve is connected with the trap valve. According to the system and the method, the primary loop is heated via the evaporator by utilizing external steam, so that temperature of the primary loop reaches the required temperature for the hot test in a short time, thereby greatly shortening hot test time and reducing the trial operation period.
Description
Technical field:
The present invention relates to technical field of nuclear power, be specifically related to one and utilize external steam to promote one loop of nuclear power station
Temperature carries out the system and method for heat examination.
Background technology:
The main frictional heat using nuclear island main pump (main core blower fan) rotation to produce of nuclear power station heat examination at present adds hot water
(helium) promotes primary Ioops temperature, and heat produced by main pump (main core blower fan) spin friction has
Limit, primary Ioops temperature promotes slower so that the hot examination time is longer.
Summary of the invention:
Present invention aims to the examination of current nuclear power station heat and promote the limitation of primary Ioops temperature methods, carry
Supply a kind of system and method utilizing external steam lifting one loop of nuclear power station temperature to carry out heat examination.
For reaching above-mentioned purpose, the present invention adopts the following technical scheme that and realizes:
Utilize external steam promote one loop of nuclear power station temperature carry out heat examination system, including feed pump outlet every
It is filled with valve group, pressure vessel from door, high-pressure heater shunt valve, vaporizer, main inlet throttle-stop valve, external steam
And hydrophobic valve, wherein:
The outlet of feed pump outlet isolating door is connected on the entrance of high-pressure heater shunt valve, feed pump outlet every
On feedwater piping behind the door, perforate is installed external steam and is filled with valve group；
The outlet of pressure vessel is connected on the first entrance of vaporizer, and the first outlet of vaporizer is connected on pressure vessel
Entrance, the outlet of high-pressure heater shunt valve is connected on the second entrance of vaporizer；
Working medium in pressure vessel is driven by the Power Drive Unit in pressure vessel, for compressed water reactor nuclear power
For standing, its working medium is demineralized water, and driving means is main pump, for HTGR Nuclear Power Plant, its
Working medium is helium, and driving means is Helium fan；Vaporizer is shell-and-tube heat exchanger, and shell-side is vaporizer
Primary side, tube side is the secondary side of vaporizer, and the first entrance of vaporizer accesses the primary side of vaporizer, steams
Sending out the primary side outlet that the first outlet is vaporizer of device, the second entrance of vaporizer accesses the secondary of vaporizer
Side entrance, the secondary side outlet of vaporizer is connected on the second outlet of vaporizer；It is connected with vaporizer primary side
System become primary Ioops, the system being connected with vaporizer secondary side becomes secondary circuit；
The entrance of main inlet throttle-stop valve is connected on the second outlet of vaporizer, and the live steam piping before main inlet throttle-stop valve connects drain valve
Door.
The present invention is further improved by, and external steam is filled with valve group and includes connecting successively against filling vapour direction
Non-return flap, regulation door and the cut-off gate connect.
The present invention is further improved by, before hydrophobic valve includes main inlet throttle-stop valve, and feed pump outlet isolating door
After secondary circuit on all hydrophobic valves.
Utilize external steam to promote the method that one loop of nuclear power station temperature carries out heat examination, comprise the following steps:
1) feed pump is exported isolating door, main inlet throttle-stop valve is closed tight, opens hydrophobic valve；
2) external steam is filled with valve group by external steam and is filled with high-pressure heater shunt valve, vaporizer
Secondary side until before main inlet throttle-stop valve, hydrophobic is discharged by hydrophobic valve；
3) in being filled with steam course, being filled with of gate control steam is regulated by what external steam was filled with in valve group
, there is not water slug, and ensure that the temperature rise speed of vaporizer is less than its temperature in speed, it is ensured that steam is filled with gently
Rise limit value；
4) after the steam discharged from hydrophobic valve is without water, close hydrophobic valve, subsequently secondary circuit pressure,
Temperature will slowly rise, in intensification, boost process, it is ensured that the intensification of vaporizer, the rate of rise are less than it
Temperature, pressure limit；
5) start the driving means in pressure vessel, rotated by driving means and make primary Ioops working medium circulation stream
Moving up, primary Ioops working medium absorbs the heat of secondary circuit steam, and temperature slowly raises, meanwhile, and driving means
Frictional heat, heats the working medium of primary Ioops further；
6) along with the lifting of secondary circuit temperature, primary Ioops temperature the most slowly promotes, when secondary circuit, primary Ioops temperature
Spend close to after external steam temperature, stop being filled with steam to secondary circuit, and close external steam and be filled with valve
The pitch of group and cut-off gate, now external steam is filled with the non-return flap of valve group and closes the most immediately, at secondary circuit
In state of isolation；
7) primary Ioops driving means continues to rotate, and the heat that its spin friction produces heats further to primary Ioops,
Until primary Ioops temperature meets the requirement of heat examination.
The present invention is further improved by, and external steam is starting trouble steam, heating boiler steam or neighbour
Machine auxiliary steam.
Compared with prior art, present invention have the advantage that:
What the present invention provided utilizes external steam lifting one loop of nuclear power station temperature to carry out system and the side of heat examination
Method.Wherein, this system has a following clear advantage:
(1) external steam temperature typically has about 200 DEG C, utilizes external steam to pass through secondary circuit back heating one
Loop is to the temperature close to external steam, it is only necessary to utilize main pump (main core blower fan) to rotate primary Ioops work
Matter rises to, from about 200 DEG C, the temperature that heat examination needs, needed for thus greatly reducing lifting primary Ioops working medium
The time wanted, thus shorten the hot examination time, decrease the nuclear power generating sets test run duration.
(2) for HTGR, during heat is tried, secondary circuit is full of nitrogen, now secondary circuit gas
Atmosphere and properly functioning atmosphere difference are relatively big, and if secondary circuit is steam, then with actual motion atmosphere ratio
Relatively similar, therefore heat examination effect is more preferable；Steam price for nitrogen is lower, and therefore cost is lower；
Steam will not produce risk of suffocating, the most safer.
(3) this system mainly make use of the original equipment of nuclear power station, and the extra equipment increased is less, invests into
This is few.
The method and currently used method have compared following clear advantage:
(1) external steam temperature typically has about 200 DEG C, utilizes external steam to pass through secondary circuit back heating one
Loop is to the temperature close to external steam, it is only necessary to utilize main pump (main core blower fan) to rotate primary Ioops work
Matter rises to, from about 200 DEG C, the temperature that heat examination needs, needed for thus greatly reducing lifting primary Ioops working medium
The time wanted, thus shorten the hot examination time, decrease the nuclear power generating sets test run duration.
(2) for HTGR, during heat is tried, secondary circuit is full of nitrogen, now secondary circuit gas
Atmosphere and properly functioning atmosphere difference are relatively big, and if secondary circuit is steam, then with actual motion atmosphere ratio
Relatively similar, therefore heat examination effect is more preferable；Steam price for nitrogen is lower, and therefore cost is lower；
Steam will not produce risk of suffocating, the most safer.
Accompanying drawing illustrates:
Fig. 1 is that the present invention utilizes external steam to promote the structure that one loop of nuclear power station temperature carries out the system of heat examination
Block diagram.
Detailed description of the invention:
Below in conjunction with accompanying drawing, the present invention is made further instructions.
As it is shown in figure 1, the external steam lifting one loop of nuclear power station temperature that utilizes that the present invention provides carries out heat examination
System, including feed pump outlet isolating door 1, high-pressure heater shunt valve 2, vaporizer 3, main inlet throttle-stop valve 4,
External steam is filled with valve group 5, pressure vessel 6 and hydrophobic valve 7, wherein: feed pump outlet isolating door 1
Outlet be connected on the entrance of high-pressure heater shunt valve 2, the feedwater piping after feed pump outlet isolating door 1
Upper perforate is installed external steam and is filled with valve group 5；The outlet of pressure vessel 6 is connected on the first entrance of vaporizer 3,
First outlet of vaporizer 3 is connected on the entrance of pressure vessel, and the outlet of high-pressure heater shunt valve 2 is connected on steaming
Send out the second entrance of device 3；Working medium in pressure vessel 6 is driven by the Power Drive Unit in pressure vessel 6
Dynamic, for pressurized-water reactor nuclear power plant, its working medium is demineralized water, and driving means is main pump, for High Temperature Gas
For cold dome nuclear power station, its working medium is helium, and driving means is Helium fan；Vaporizer 3 changes for shell-and-tube
Hot device, shell-side is the primary side of vaporizer 3, and tube side is the secondary side of vaporizer 3, the first of vaporizer 3
Entrance accesses the primary side of vaporizer 3, the primary side outlet that the first outlet is vaporizer 3 of vaporizer 3,
Second entrance of vaporizer 3 accesses the secondary side entrance of vaporizer 3, and the secondary side outlet of vaporizer 3 is connected on
Second outlet of vaporizer 3；The system being connected with vaporizer primary side becomes primary Ioops, with vaporizer two
The system that secondary side connects becomes secondary circuit；The entrance of main inlet throttle-stop valve 4 is connected on the second outlet of vaporizer 3, is leading
Hydrophobic valve 7 is connect on live steam piping before porthole 4.
What the present invention provided utilizes external steam to promote the method that one loop of nuclear power station temperature carries out heat examination, specifically
Comprise the following steps:
1) feed pump exports isolating door 1, main inlet throttle-stop valve 4 is 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, evaporation
The secondary side of device 3 until before main inlet throttle-stop valve 4, hydrophobic is discharged by hydrophobic valve 7；
3) in being filled with steam course, filling of gate control steam is regulated by what external steam was filled with in valve group 5
Enter speed, it is ensured that steam is filled with gently, water slug does not occur, and ensures that the temperature rise speed of vaporizer 3 is less than
Its temperature limit；
4) after the steam discharged from hydrophobic valve 7 is without water, hydrophobic valve 7, subsequently secondary circuit pressure are closed
Power, temperature will slowly rise, in intensification, boost process, it is ensured that the intensification of vaporizer 3, the rate of rise
Less than its temperature, pressure limit；
5) start the driving means in pressure vessel 6, rotated by driving means and make primary Ioops working medium circulation
Flowing, primary Ioops working medium absorbs the heat of secondary circuit steam, and temperature slowly raises, and meanwhile, drives dress
Put frictional heat, heat the working medium of primary Ioops further；
6) along with the lifting of secondary circuit temperature, primary Ioops temperature the most slowly promotes, when secondary circuit, primary Ioops temperature
Spend close to after external steam temperature, stop being filled with steam to secondary circuit, and close external steam and be filled with valve
The pitch of group 5 and cut-off gate, now external steam is filled with the non-return flap of valve group 5 and closes the most immediately, two times
Road is in state of isolation；
7) primary Ioops driving means continues to rotate, and the heat that its spin friction produces heats further to primary Ioops,
Until primary Ioops temperature meets the requirement of heat examination.
As a example by promoting primary Ioops temperature during certain nuclear power generating sets heat is tried below, the concrete real of this invention is described
Execute mode.
The available outside vapour source of this unit include 1 can produce 42t/h parameter be 1.25MPa, 193 DEG C
The electric boiler of steam and can produce 10t/h parameter be 1.25MPa, the coal-burning boiler of 193 DEG C of steam 5.
Total steam production is 92t/h.The power of this unit main pump (main core blower fan) is 4500KW.
1) feed pump exports isolating door 1, main inlet throttle-stop valve 4 is closed tight, opens all hydrophobic valves of secondary circuit；
2) external steam is filled with valve group 5 by external steam and is filled with high-pressure heater shunt valve 2, evaporation
The secondary side of device 3 until before main inlet throttle-stop valve 4, hydrophobic is discharged by secondary circuit hydrophobic valve；
3) in being filled with steam course, filling of gate control steam is regulated by what external steam was filled with in valve group 5
Enter speed, it is ensured that steam is filled with gently, water slug does not occur, and ensures that the temperature rise speed of vaporizer 3 is less than
Its temperature limit；
4) after the steam discharged from hydrophobic valve is without water, close hydrophobic valve, subsequently secondary circuit pressure,
Temperature will slowly rise, in intensification, boost process, it is ensured that the intensification of vaporizer 3, the rate of rise are less than
Its temperature, pressure limit；
5) start the driving means in pressure vessel 6, rotated by driving means and make primary Ioops working medium circulation
Flowing, primary Ioops working medium absorbs the heat of secondary circuit steam, and temperature slowly raises, and meanwhile, drives dress
Put frictional heat, heat the working medium of primary Ioops further；
6) along with the lifting of secondary circuit temperature, primary Ioops temperature the most slowly promotes, when secondary circuit, primary Ioops temperature
Spend close to after external steam temperature 193 DEG C, stop being filled with steam to secondary circuit, and close external steam and be filled with
The pitch of valve group 5 and cut-off gate, now external steam is filled with the non-return flap of valve group 5 and closes the most immediately,
Secondary circuit is in state of isolation；
7) primary Ioops driving means continues to rotate, and the heat that its spin friction produces heats further to primary Ioops,
Until primary Ioops temperature meets the requirement (250 DEG C) of heat examination.
By this method, main pump (main core blower fan) is utilized only to need from 193 DEG C, system is heated to 250 DEG C,
Conventional method then needs from room temperature, system is heated to 250 DEG C.And for HTGR, due to
Its secondary circuit is steam, and closer to actual operating mode, heat examination effect is more preferable, safer, cost is lower
(relative to secondary circuit inflated with nitrogen).
Claims (5)
1. utilize external steam to promote one loop of nuclear power station temperature and carry out the system of heat examination, it is characterised in that bag
Include feed pump outlet isolating door (1), high-pressure heater shunt valve (2), vaporizer (3), main inlet throttle-stop valve (4),
External steam is filled with valve group (5), pressure vessel (6) and hydrophobic valve (7), wherein:
The outlet of feed pump outlet isolating door (1) is connected on the entrance of high-pressure heater shunt valve (2), is giving
On feedwater piping after exit of pump isolating door (1), perforate is installed external steam and is filled with valve group (5)；
The outlet of pressure vessel (6) is connected on the first entrance of vaporizer (3), and the first of vaporizer (3) goes out
Mouth is connected on the entrance of pressure vessel, and the outlet of high-pressure heater shunt valve (2) is connected on the of vaporizer (3)
Two entrances；
Working medium in pressure vessel (6) is driven by the Power Drive Unit in pressure vessel (6), for
For pressurized-water reactor nuclear power plant, its working medium is demineralized water, and driving means is main pump, for HTGR nuclear power
For standing, its working medium is helium, and driving means is Helium fan；Vaporizer (3) is shell-and-tube heat exchanger,
Shell-side is the primary side of vaporizer (3), and tube side is the secondary side of vaporizer (3), the of vaporizer (3)
One entrance accesses the primary side of vaporizer (3), and the first outlet of vaporizer (3) is the one of vaporizer (3)
Secondary side outlet, the second entrance of vaporizer (3) accesses the secondary side entrance of vaporizer (3), vaporizer (3)
Secondary side outlet be connected on vaporizer (3) second outlet；The system being connected with vaporizer primary side becomes
Primary Ioops, the system being connected with vaporizer secondary side becomes secondary circuit；
The entrance of main inlet throttle-stop valve (4) is connected on the second outlet of vaporizer (3), at the main vapour that main inlet throttle-stop valve (4) is front
Hydrophobic valve (7) is connect on pipeline.
The most according to claim 1 utilize external steam promote one loop of nuclear power station temperature carry out heat examination
System, it is characterised in that external steam is filled with valve group (5) and includes inverse against fill that vapour direction is sequentially connected with
Only door, regulation door and cut-off gate.
The most according to claim 1 utilize external steam promote one loop of nuclear power station temperature carry out heat examination
System, it is characterised in that before hydrophobic valve (7) includes main inlet throttle-stop valve (4), feed pump outlet isolating door
(1) all hydrophobic valves on the secondary circuit after.
4. utilize external steam to promote the method that one loop of nuclear power station temperature carries out heat examination, it is characterised in that bag
Include following steps:
1) feed pump exports isolating door (1), main inlet throttle-stop valve (4) is 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),
The secondary side of vaporizer (3) is until main inlet throttle-stop valve (4) is front, hydrophobic by hydrophobic valve (7) discharge；
3) the regulation gate control steam being filled with in valve group (5) by external steam in being filled with steam course
Be filled with speed, it is ensured that steam is filled with gently, and water slug do not occurs, and ensures the temperature rise speed of vaporizer (3)
Degree is less than its temperature limit；
4) after the steam discharged from hydrophobic valve (7) is without water, hydrophobic valve (7) is closed, subsequently two
Circuit pressure, temperature will slowly rise, and heat up, in boost process, it is ensured that the intensification of vaporizer (3),
The rate of rise is less than its temperature, pressure limit；
5) start the driving means in pressure vessel (6), rotated by driving means and make primary Ioops working medium
Circulating, primary Ioops working medium absorbs the heat of secondary circuit steam, and temperature slowly raises, and, drives meanwhile
Dynamic device frictional heat, heats the working medium of primary Ioops further；
6) along with the lifting of secondary circuit temperature, primary Ioops temperature the most slowly promotes, when secondary circuit, primary Ioops temperature
Spend close to after external steam temperature, stop being filled with steam to secondary circuit, and close external steam and be filled with valve
The pitch of group (5) and cut-off gate, now external steam is filled with the non-return flap of valve group (5) and closes the most immediately,
Secondary circuit is in state of isolation；
7) primary Ioops driving means continues to rotate, and the heat that its spin friction produces heats further to primary Ioops,
Until primary Ioops temperature meets the requirement of heat examination.
The most according to claim 4 utilize external steam promote one loop of nuclear power station temperature carry out heat examination
Method, it is characterised in that external steam is that starting trouble steam, heating boiler steam or adjacent machine auxiliary are steamed
Vapour.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201610496470.0A CN105957570B (en) | 2016-06-28 | 2016-06-28 | The system and method that one loop of nuclear power station temperature carries out heat examination is lifted using external steam |
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| CN201610496470.0A CN105957570B (en) | 2016-06-28 | 2016-06-28 | The system and method that one loop of nuclear power station temperature carries out heat examination is lifted using external steam |
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Cited By (4)
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| CN106981322A (en) * | 2017-04-26 | 2017-07-25 | 西安热工研究院有限公司 | A kind of system and method for being used to verify HTGR 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 |
| CN112209414A (en) * | 2020-09-01 | 2021-01-12 | 靖西天桂铝业有限公司 | Linkage hot test process before production of aluminum oxide |
| WO2022016869A1 (en) * | 2020-07-21 | 2022-01-27 | 西安热工研究院有限公司 | System and method for heating primary coolant circuit compartment during cold test of high-temperature gas-cooled reactor nuclear power plant |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN106981322A (en) * | 2017-04-26 | 2017-07-25 | 西安热工研究院有限公司 | A kind of system and method for being used to verify HTGR start and stop heaping equipment function |
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| 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 |
| WO2022016869A1 (en) * | 2020-07-21 | 2022-01-27 | 西安热工研究院有限公司 | System and method for heating primary coolant circuit compartment during cold test of high-temperature gas-cooled reactor nuclear power plant |
| CN112209414A (en) * | 2020-09-01 | 2021-01-12 | 靖西天桂铝业有限公司 | Linkage hot test process before production of aluminum oxide |
| 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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|---|---|
| CN105957570B (en) | 2017-10-03 |
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