CN108278586A - A kind of system and method for HTGR Nuclear Power Plant primary Ioops heating and dehumidification - Google Patents
A kind of system and method for HTGR Nuclear Power Plant primary Ioops heating and dehumidification Download PDFInfo
- Publication number
- CN108278586A CN108278586A CN201810210973.6A CN201810210973A CN108278586A CN 108278586 A CN108278586 A CN 108278586A CN 201810210973 A CN201810210973 A CN 201810210973A CN 108278586 A CN108278586 A CN 108278586A
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- China
- Prior art keywords
- evaporator
- valve
- steam
- primary ioops
- filled
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
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- 238000010438 heat treatment Methods 0.000 title claims abstract description 39
- 238000007791 dehumidification Methods 0.000 title claims abstract description 25
- 238000000034 method Methods 0.000 title claims abstract description 17
- 230000002209 hydrophobic effect Effects 0.000 claims abstract description 28
- 239000001307 helium Substances 0.000 claims description 9
- 229910052734 helium Inorganic materials 0.000 claims description 9
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims description 9
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 6
- 238000002955 isolation Methods 0.000 claims description 4
- 238000010025 steaming Methods 0.000 claims 2
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 10
- 239000003575 carbonaceous material Substances 0.000 description 6
- 229910052757 nitrogen Inorganic materials 0.000 description 5
- 230000000694 effects Effects 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 239000012535 impurity Substances 0.000 description 2
- 206010003497 Asphyxia Diseases 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- 239000011248 coating agent Substances 0.000 description 1
- 238000000576 coating method Methods 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000006731 degradation reaction Methods 0.000 description 1
- 230000003111 delayed effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000000605 extraction Methods 0.000 description 1
- 230000017525 heat dissipation Effects 0.000 description 1
- 238000009413 insulation Methods 0.000 description 1
- 239000000314 lubricant Substances 0.000 description 1
- 238000001179 sorption measurement Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/08—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being steam
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B3/00—Other methods of steam generation; Steam boilers not provided for in other groups of this subclass
- F22B3/06—Other methods of steam generation; Steam boilers not provided for in other groups of this subclass by transformation of mechanical, e.g. kinetic, energy into heat energy
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
-
- 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
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Life Sciences & Earth Sciences (AREA)
- Sustainable Development (AREA)
- Sustainable Energy (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Drying Of Gases (AREA)
Abstract
A kind of system and method for HTGR Nuclear Power Plant primary Ioops heating and dehumidification of the present invention, the system include that evaporator inlet isolating valve, evaporator, main inlet throttle-stop valve, hydrophobic valve, pressure vessel and external steam are filled with valve group, wherein:Evaporator inlet isolating valve, evaporator, main inlet throttle-stop valve are sequentially connected, and have drain valve between evaporator inlet isolating valve, evaporator, and connecing external steam on pipeline between evaporator, main inlet throttle-stop valve is filled with valve group.This method is that external steam is filled with valve group by external steam to be filled into evaporator secondary side, and primary Ioops working medium is heated in evaporator, improves primary Ioops temperature, meets the requirement of primary Ioops heating and dehumidification.
Description
Technical field
The invention belongs to technical field of nuclear power, and in particular to a kind of HTGR Nuclear Power Plant primary Ioops heating and dehumidification is
System and method.
Background technology
There are a large amount of carbon materials in HTGR Nuclear Power Plant primary Ioops in-pile component, contains in these carbon materials
Large quantity micropore gap, hole is removed from impurity such as ambient enviroment adsorption moistures if not carrying out heating to reactor core carbon materials under room temperature
Wet, the impurity such as moisture will occur chemical attack with carbon materials under the hot conditions of reactor operation and react, to influence heap
Interior carbon materials intensity and reactor safety, and it is possible in control rod drive mechanism, absorb ball driving mechanism, Helium fan
The cold ends such as motor cavity condense, cause degradation of insulation, lubricant coating corrosion the problems such as, endanger equipment safety.To avoid moisture shadow
It rings, it is necessary to which the method for taking heating and dehumidification removes the moisture of carbon materials.
HTGR Nuclear Power Plant primary Ioops heating at present promotes one mainly by the frictional heat of main core wind turbine rotation generation
Loop temperature, this method are primarily present problems with:
1) due to thermal Finite caused by main core wind turbine spin friction, primary Ioops temperature is promoted slower;
2) primary Ioops radiate outward while Helium fan spin friction heat, and the equalization point of heat, which is to reach, to be added
The limiting temperature of heat, heats, is extremely difficult to preferably remove wet temp in this way;
3) while primary Ioops heating and dehumidification, secondary circuit needs nitrogen filled protection, and nitrogen charging cost is higher, and to work around
The safety for making personnel has an impact;
4) after secondary circuit nitrogen charging, while primary Ioops heat, secondary circuit is also heated, while also heat dissipation outward, is increased
Primary Ioops promote the difficulty of temperature.
Invention content
It is an object of the invention to the limitations for current HTGR Nuclear Power Plant heating and dehumidifying system and method, carry
A kind of system and method for HTGR Nuclear Power Plant primary Ioops heating and dehumidification is supplied.
The present invention adopts the following technical scheme that realize:
A kind of system of HTGR Nuclear Power Plant primary Ioops heating and dehumidification, including evaporator inlet isolating valve, evaporator,
Main inlet throttle-stop valve, hydrophobic valve, pressure vessel and external steam are filled with valve group, wherein:
The outlet of evaporator inlet isolating valve is connected on the second entrance of evaporator, the outlet of evaporator inlet isolating valve with
Hydrophobic valve is connect on the pipeline of the second entrance of evaporator;
The entrance of main inlet throttle-stop valve is connected on the second outlet of evaporator, and connecing external steam on the live steam piping before main inlet throttle-stop valve is 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;
Helium in pressure vessel is driven by the Helium fan in pressure vessel;Evaporator is shell-and-tube heat exchanger, shell
Side is the primary side of evaporator, and pipe side is the secondary side of evaporator, and the primary side of the first entrance access evaporator of evaporator steams
The first outlet for sending out device is a side outlet of evaporator, and the secondary side entrance of the second entrance access evaporator of evaporator is steamed
The secondary side outlet of hair device is connected on the second outlet of evaporator;The system being connected with evaporator primary side becomes primary Ioops, with
The system of evaporator secondary side connection becomes secondary circuit.
The present invention, which further improves, to be, it includes sequentially connected inverse against vapour direction is filled that external steam, which is filled with valve group,
Only door, adjusting door and cut-off gate.
The present invention, which further improves, to be, before hydrophobic valve includes evaporator, two after evaporator inlet isolating valve
All hydrophobic valves on circuit.
A kind of method of HTGR Nuclear Power Plant primary Ioops heating and dehumidification, includes the following steps:
1) evaporator inlet isolating valve, main inlet throttle-stop valve are closed tight, opens hydrophobic valve;
2) external steam is filled with the secondary side that valve group is filled with evaporator by external steam, it is hydrophobic to pass through hydrophobic valve
Discharge;
3) the adjusting gate steam processed being filled in valve group by external steam in being filled with steam course is filled with speed,
Ensure that steam is filled with gently, water slug does not occur, and ensures that the temperature rise speed of evaporator is less than its temperature limit;
4) after the steam being discharged from hydrophobic valve is without water, hydrophobic valve is closed, subsequent secondary circuit pressure, temperature will be delayed
It is slow to rise, in heating, boost process, ensure that the heating of evaporator, the rate of rise are less than its temperature, pressure limit;
5) start the driving device in pressure vessel, rotated by driving device so that primary Ioops working medium circulation flows
To come, primary Ioops working medium absorbs the heat of secondary circuit steam, and temperature slowly increases, meanwhile, driving device frictional heat further adds
The working medium of hot primary Ioops;
6) with the promotion of secondary circuit temperature, primary Ioops temperature is also slowly promoted, 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 driving device continues to rotate, and the heat that spin friction generates gives primary Ioops further heating and dehumidification,
Until the requirement of primary Ioops dehumidifying.
The present invention, which further improves, to be, external steam is starting trouble steam, heating boiler steam or adjacent machine auxiliary
Steam.
The present invention has the advantage that:
A kind of system and method for HTGR Nuclear Power Plant primary Ioops heating and dehumidification provided by the invention.Wherein, have
Following clear advantage:
1, HTGR Nuclear Power Plant is being built at present, Helium fan power only has 4300KW, and the power of external electric boiler
The steam for being 27000KW, being 6 times of main core wind turbine, therefore generated using electric boiler heats primary Ioops to carry out by secondary circuit
The heating and dehumidification of primary Ioops can greatly promote the speed of primary Ioops heating, save the duration;
2, electric boiler outlet steam temperature can reach 300 DEG C, pass through secondary circuit back heating primary Ioops using external steam
Ideal heating and dehumidification temperature can be reached, effect on moisture extraction is good;
3, for high temperature gas cooled reactor, during primary Ioops heating and dehumidification, secondary circuit is full of nitrogen, at this time secondary circuit gas
The atmosphere difference of atmosphere and normal operation is larger, and if secondary circuit is vapor, it is similar with actual motion atmosphere, therefore
It is more preferable to debug test run effect;Vapor price for nitrogen is lower, therefore cost is lower;Vapor not will produce asphyxia
Risk, it is also safer.
4, it is filled with steam from evaporator outlet, hydrophobic from evaporator inlet discharge, the secondary circuit for meeting evaporator design goes out
Mouth temperature is high, the low feature of inlet temperature so that evaporator inlet-outlet is in the temperature range of safety always;
5, the original equipment of nuclear power station is mainly utilized in the system, and additional increased equipment is less, and cost of investment is few.
Description of the drawings
Fig. 1 is a kind of structure diagram of the system of HTGR Nuclear Power Plant primary Ioops heating and dehumidification of the present invention.
In figure:1- evaporator inlet isolating valves, 2- evaporators, 3- main inlet throttle-stop valves, 4- hydrophobic valves, 5- pressure vessels, outside 6-
Portion's steam is filled with valve group.
Specific implementation mode
The present invention is made further instructions below in conjunction with attached drawing.
As shown in Figure 1, a kind of system of HTGR Nuclear Power Plant primary Ioops heating and dehumidification provided by the invention, including steam
Hair device inlet isolation valve 1, evaporator 2, main inlet throttle-stop valve 3, hydrophobic valve 4, pressure vessel 5 and external steam are filled with valve group 6.
The outlet of evaporator inlet isolating valve 1 is connected on the second entrance of evaporator 2, in going out for evaporator inlet isolating valve 1
Mouth connects hydrophobic valve 4 on the pipeline of the second entrance of evaporator 2;The entrance of main inlet throttle-stop valve 3 is connected on the second outlet of evaporator 2,
External steam is connect on live steam piping before main inlet throttle-stop valve 3 is filled with valve group 6;The outlet of pressure vessel 5 is connected on the first of evaporator 2
The first outlet of entrance, evaporator 2 is connected on the entrance of pressure vessel;Helium in pressure vessel 5 passes through the master in pressure vessel 5
Helium circulator drives;Evaporator 2 is shell-and-tube heat exchanger, and shell-side is the primary side of evaporator 2, and pipe side is the secondary side of evaporator 2,
The primary side of the first entrance access evaporator 2 of evaporator 2, the first outlet of evaporator 2 is a side outlet of evaporator 2,
The secondary side entrance of the second entrance access evaporator 2 of evaporator 2, the secondary side outlet of evaporator 2 are connected on the second of evaporator 2
Outlet;The system being connected with evaporator primary side becomes primary Ioops, and the system being connect with evaporator secondary side becomes secondary circuit.
Wherein, it includes against filling the sequentially connected non-return flap in vapour direction, adjust door and cut-off that external steam, which is filled with valve group 6,
Door.Before hydrophobic valve 4 includes evaporator 2, all hydrophobic valves on the secondary circuit after evaporator inlet isolating valve 1.
A kind of method of HTGR Nuclear Power Plant primary Ioops heating and dehumidification provided by the invention, includes the following steps:
1) evaporator inlet isolating valve 1, main inlet throttle-stop valve 3 are closed tight, opens hydrophobic valve 4;
2) external steam is filled with the secondary side that valve group 6 is filled with evaporator 2 by external steam, it is hydrophobic to pass through drain valve
Door 4 is discharged;Wherein, external steam is starting trouble steam, heating boiler steam or adjacent machine auxiliary steam;
3) the adjusting gate steam processed being filled in valve group 6 by external steam in being filled with steam course is filled with speed
Degree, ensures that steam is filled with gently, water slug does not occur, and ensures that the temperature rise speed of evaporator 2 is less than its temperature limit;
4) after the steam being discharged from hydrophobic valve 4 is without water, hydrophobic valve 4 is closed, subsequent secondary circuit pressure, temperature will
Slowly rise, in heating, boost process, ensures that the heating of evaporator 2, the rate of rise are less than its temperature, pressure limit;
5) start the driving device in pressure vessel 5, rotated by driving device so that primary Ioops working medium circulation flows
To come, primary Ioops working medium absorbs the heat of secondary circuit steam, and temperature slowly increases, meanwhile, driving device frictional heat further adds
The working medium of hot primary Ioops;
6) with the promotion of secondary circuit temperature, primary Ioops temperature is also slowly promoted, 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 6,
External steam is filled with the non-return flap of valve group 6 and also closes immediately at this time, and secondary circuit is in state of isolation;
7) primary Ioops driving device continues to rotate, and the heat that spin friction generates gives primary Ioops further heating and dehumidification,
Until the requirement of primary Ioops dehumidifying.
Claims (5)
1. a kind of system of HTGR Nuclear Power Plant primary Ioops heating and dehumidification, which is characterized in that be isolated including evaporator inlet
Valve (1), evaporator (2), main inlet throttle-stop valve (3), hydrophobic valve (4), pressure vessel (5) and external steam are filled with valve group (6),
In:
The outlet of evaporator inlet isolating valve (1) is connected on the second entrance of evaporator (2), in evaporator inlet isolating valve (1)
Outlet connects hydrophobic valve (4) on the pipeline of the second entrance of evaporator (2);
The entrance of main inlet throttle-stop valve (3) is connected on the second outlet of evaporator (2), and external steaming is connect on the live steam piping before main inlet throttle-stop valve (3)
Vapour is filled with valve group (6);
The outlet of pressure vessel (5) is connected on the first entrance of evaporator (2), and the first outlet of evaporator (2) is connected on pressure vessel
Entrance;
Helium in pressure vessel (5) is driven by the Helium fan in pressure vessel (5);Evaporator (2) is pipe shell type heat exchange
Device, shell-side are the primary side of evaporator (2), and pipe side is the secondary side of evaporator (2), and the first entrance access of evaporator (2) is steamed
The primary side of device (2) is sent out, the first outlet of evaporator (2) is a side outlet of evaporator (2), and the second of evaporator (2) enters
The secondary side entrance of mouth access evaporator (2), the secondary side outlet of evaporator (2) are connected on the second outlet of evaporator (2);With steaming
The system that hair device primary side is connected becomes primary Ioops, and the system being connect with evaporator secondary side becomes secondary circuit.
2. a kind of system of HTGR Nuclear Power Plant primary Ioops heating and dehumidification according to claim 1, which is characterized in that
It includes against filling the sequentially connected non-return flap in vapour direction, adjust door and cut-off gate that external steam, which is filled with valve group (6),.
3. a kind of system of HTGR Nuclear Power Plant primary Ioops heating and dehumidification according to claim 1, which is characterized in that
Before hydrophobic valve (4) includes evaporator (2), all hydrophobic valves on secondary circuit after evaporator inlet isolating valve (1).
4. a kind of method of HTGR Nuclear Power Plant primary Ioops heating and dehumidification, which is characterized in that include the following steps:
1) evaporator inlet isolating valve (1), main inlet throttle-stop valve (3) are closed tight, opens hydrophobic valve (4);
2) external steam is filled with the secondary side that valve group (6) is filled with evaporator (2) by external steam, it is hydrophobic to pass through drain valve
Door (4) discharge;
3) the adjusting gate steam processed being filled in valve group (6) by external steam in being filled with steam course is filled with speed,
Ensure that steam is filled with gently, water slug does not occur, and ensures that the temperature rise speed of evaporator (2) is less than its temperature limit;
4) after the steam being discharged from hydrophobic valve (4) is without water, hydrophobic valve (4) is closed, subsequent secondary circuit pressure, temperature will
Slowly rise, in heating, boost process, ensures that the heating of evaporator (2), the rate of rise are less than its temperature, pressure limit;
5) start the driving device in pressure vessel (5), rotated by driving device and primary Ioops working medium circulation is flowed,
Primary Ioops working medium absorbs the heat of secondary circuit steam, and temperature slowly increases, meanwhile, driving device frictional heat further heats
The working medium of primary Ioops;
6) with the promotion of secondary circuit temperature, primary Ioops temperature is also slowly promoted, when secondary circuit, primary Ioops temperature are close to outside
After 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 (6), this
When external steam be filled with the non-return flap of valve group (6) and also close immediately, secondary circuit is in state of isolation;
7) primary Ioops driving device continues to rotate, and the heat that spin friction generates gives primary Ioops further heating and dehumidification, until
The requirement of primary Ioops dehumidifying.
5. a kind of method of HTGR Nuclear Power Plant primary Ioops heating and dehumidification according to claim 4, which is characterized in that
External steam is starting trouble steam, heating boiler steam or adjacent machine auxiliary steam.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
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CN201810210973.6A CN108278586A (en) | 2018-03-14 | 2018-03-14 | A kind of system and method for HTGR Nuclear Power Plant primary Ioops heating and dehumidification |
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CN201810210973.6A CN108278586A (en) | 2018-03-14 | 2018-03-14 | A kind of system and method for HTGR Nuclear Power Plant primary Ioops heating and dehumidification |
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CN201810210973.6A Pending CN108278586A (en) | 2018-03-14 | 2018-03-14 | A kind of system and method for HTGR Nuclear Power Plant primary Ioops heating and dehumidification |
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Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
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 |
CN114909645A (en) * | 2022-06-06 | 2022-08-16 | 华能山东石岛湾核电有限公司 | Primary side cleaning system and method for high temperature gas cooled reactor steam generator |
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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 |
CN114909645A (en) * | 2022-06-06 | 2022-08-16 | 华能山东石岛湾核电有限公司 | Primary side cleaning system and method for high temperature gas cooled reactor steam generator |
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Application publication date: 20180713 |