CN205789136U - Utilize external steam to promote one loop of nuclear power station temperature and carry out the system of heat examination - Google Patents
Utilize external steam to promote one loop of nuclear power station temperature and carry out the system of heat examination Download PDFInfo
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- CN205789136U CN205789136U CN201620666893.8U CN201620666893U CN205789136U CN 205789136 U CN205789136 U CN 205789136U CN 201620666893 U CN201620666893 U CN 201620666893U CN 205789136 U CN205789136 U CN 205789136U
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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
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Abstract
A kind of system utilizing external steam lifting one loop of nuclear power station temperature to carry out heat examination of this utility model, it is filled with valve group, pressure vessel and hydrophobic valve including feed pump outlet isolating door, high-pressure heater shunt valve, vaporizer, main inlet throttle-stop valve, external steam, wherein: the outlet of feed pump outlet isolating door is connected on the entrance of high-pressure heater shunt valve, on the feedwater piping after feed pump outlet isolating door, perforate is installed external steam and is filled with valve group；The outlet of pressure vessel is connected on the primary side entrance of vaporizer, and the primary side outlet of vaporizer 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 vaporizer；The entrance of main inlet throttle-stop valve is connected on the secondary side outlet of vaporizer, and the live steam piping before main inlet throttle-stop valve connects hydrophobic valve.This utility model utilizes external steam to heat primary Ioops by vaporizer so that it is temperature required that primary Ioops temperature reaches heat examination in the short period, substantially reduces the hot examination time, reduces the test run duration.
Description
Technical field:
This utility model relates to technical field of nuclear power, is specifically related to one and utilizes external steam to promote one loop of nuclear power station temperature
Degree carries out the system of 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)
Promoting primary Ioops temperature, thermal Finite produced by main pump (main core blower fan) spin friction, primary Ioops temperature promotes relatively
Slowly so that the hot examination time is longer.
Utility model content:
The purpose of this utility model is to promote the limitation of primary Ioops temperature methods for the examination of current nuclear power station heat, it is provided that
A kind of utilize external steam to promote one loop of nuclear power station temperature to carry out the system of heat examination.
For reaching above-mentioned purpose, this utility model 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 isolating door,
High-pressure heater shunt valve, vaporizer, main inlet throttle-stop valve, external steam are filled with valve group, pressure vessel and hydrophobic valve, wherein:
The outlet of feed pump outlet isolating door is connected on the entrance of high-pressure heater shunt valve, after feed pump outlet 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 vaporizer, and the first outlet of vaporizer is connected on entering of pressure vessel
Mouthful, 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, comes for pressurized-water reactor nuclear power plant
Saying, its working medium is demineralized water, and driving means is main pump, and for HTGR Nuclear Power Plant, its working medium is helium, drives dress
It is set to Helium fan；Vaporizer is shell-and-tube heat exchanger, and shell-side is the primary side of vaporizer, and tube side is the secondary side of vaporizer,
First entrance of vaporizer accesses the primary side of vaporizer, the primary side outlet that the first outlet is vaporizer of vaporizer, evaporation
Second entrance of device accesses the secondary side entrance of vaporizer, and the secondary side outlet of vaporizer is connected on the second outlet of vaporizer；With
The system that vaporizer primary side is connected becomes primary Ioops, and 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 hydrophobic valve.
This utility model is further improved by, and external steam is filled with valve group and includes being sequentially connected with against filling vapour direction
Non-return flap, regulation door and cut-off gate.
This utility model is further improved by, before hydrophobic valve includes main inlet throttle-stop valve, after feed pump outlet isolating door
Secondary circuit on all hydrophobic valves.
This utility model provide utilize external steam promote one loop of nuclear power station temperature carry out heat examination system, have with
Lower clear advantage:
(1) external steam temperature typically has about 200 DEG C, utilizes external steam to pass through secondary circuit back heating primary Ioops to connecing
It is bordering on the temperature of external steam, it is only necessary to utilize main pump (main core blower fan) to rotate and primary Ioops working medium risen to from about 200 DEG C
The temperature that heat examination needs, thus can greatly reduce the time promoted required for primary Ioops working medium, 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, and now secondary circuit atmosphere is with normal
The atmosphere difference run is relatively big, and if secondary circuit is steam, then relatively similar with actual motion atmosphere ratio, therefore heat examination effect
More preferably；Steam price for nitrogen is lower, and therefore cost is lower；Steam will not produce risk of suffocating, and the most more pacifies
Entirely.
(3) this system mainly make use of the original equipment of nuclear power station, and the extra equipment increased is less, and cost of investment is few.
Accompanying drawing illustrates:
Fig. 1 is that this utility model utilizes external steam to promote the structural frames that one loop of nuclear power station temperature carries out the system of heat examination
Figure.
Detailed description of the invention:
Below in conjunction with accompanying drawing, this utility model 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 this utility model provides carries out heat examination
System, is filled with valve including feed pump outlet isolating door 1, high-pressure heater shunt valve 2, vaporizer 3, main inlet throttle-stop valve 4, external steam
Group 5, pressure vessel 6 and hydrophobic valve 7, wherein: the outlet of feed pump outlet isolating door 1 is connected on high-pressure heater shunt valve 2
Entrance, on the feedwater piping after feed pump outlet isolating door 1, perforate is installed external steam and is filled with valve group 5；Pressure vessel 6
Outlet is connected on the first entrance of vaporizer 3, and the first outlet of vaporizer 3 is connected on the entrance of pressure vessel, and high-pressure heater bypasses
The outlet of pipe 2 is connected on the second entrance of vaporizer 3；Working medium in pressure vessel 6 is by the Power Drive Unit in pressure vessel 6
Driving, for pressurized-water reactor nuclear power plant, its working medium is demineralized water, and driving means is main pump, for HTGR Nuclear Power Plant
For, its working medium is helium, and driving means is Helium fan；Vaporizer 3 is shell-and-tube heat exchanger, and shell-side is the one of vaporizer 3
Secondary side, tube side is the secondary side of vaporizer 3, and the first entrance of vaporizer 3 accesses the primary side of vaporizer 3, the first of vaporizer 3
The primary side outlet that outlet is vaporizer 3, the second entrance of vaporizer 3 accesses the secondary side entrance of vaporizer 3, vaporizer 3
Secondary side outlet is connected on the second outlet of vaporizer 3；The system being connected with vaporizer primary side becomes primary Ioops, with vaporizer
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, the master before main inlet throttle-stop valve 4
Hydrophobic valve 7 is connect on steam pipe road.
The external steam lifting one loop of nuclear power station temperature that utilizes utilizing this utility model to provide carries out the hot system tried
Method, comprises the 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 two of vaporizer 3
Secondary side until before main inlet throttle-stop valve 4, hydrophobic is discharged by hydrophobic valve 7；
3) in being filled with steam course by external steam be filled with in valve group 5 regulation gate control steam be filled with speed
, there is not water slug, and ensure that the temperature rise speed of vaporizer 3 is less than its temperature limit in degree, it is ensured that steam is filled with gently；
4) after the steam discharged from hydrophobic valve 7 is without water, closing hydrophobic valve 7, secondary circuit pressure, temperature are incited somebody to action subsequently
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 primary Ioops working medium circulation is flowed
Coming, primary Ioops working medium absorbs the heat of secondary circuit steam, and temperature slowly raises, meanwhile, driving means frictional heat, add further
The working medium of hot primary Ioops；
6) along with the lifting of secondary circuit temperature, primary Ioops temperature the most slowly promotes, when secondary circuit, primary Ioops temperature close to
After external steam temperature, stop being filled with steam to secondary circuit, and close external steam and be filled with pitch and the cut-off gate of valve group 5,
Now external steam is filled with the non-return flap of valve group 5 and closes the most immediately, and 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.
As a example by promoting primary Ioops temperature during certain nuclear power generating sets heat is tried below, being embodied as of this utility model is described
Mode.
The available outside vapour source of this unit include 1 can produce 42t/h parameter be 1.25MPa, 193 DEG C of steam
Electric boiler 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.Should
The power of 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) by external steam by external steam be filled with valve group 5 be filled with high-pressure heater shunt valve 2, the two of vaporizer 3
Secondary side until before main inlet throttle-stop valve 4, hydrophobic is discharged by secondary circuit hydrophobic valve；
3) in being filled with steam course by external steam be filled with in valve group 5 regulation gate control steam be filled with speed
, there is not water slug, and ensure that the temperature rise speed of vaporizer 3 is less than its temperature limit in degree, it is ensured that steam is filled with gently；
4) after the steam discharged from hydrophobic valve is without water, closing hydrophobic valve, secondary circuit pressure, temperature will be delayed subsequently
Slow rising, 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 primary Ioops working medium circulation is flowed
Coming, primary Ioops working medium absorbs the heat of secondary circuit steam, and temperature slowly raises, meanwhile, driving means frictional heat, add further
The working medium of hot primary Ioops；
6) along with the lifting of secondary circuit temperature, primary Ioops temperature the most slowly promotes, when secondary circuit, primary Ioops temperature 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
Only door, now external steam is filled with the non-return flap of valve group 5 and closes the most immediately, and 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, and routine side
Rule needs from room temperature, system is heated to 250 DEG C.And for HTGR, owing to its secondary circuit is steam, more
Close to actual operating mode, heat examination effect is more preferable, safer, cost is lower (relative to secondary circuit inflated with nitrogen).
Claims (3)
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 include that feedwater pumps out
Mouth isolating door (1), high-pressure heater shunt valve (2), vaporizer (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 feed pump outlet isolating door (1) is connected on the entrance of high-pressure heater shunt valve (2), exports isolating door at feed pump
(1) on the feedwater piping after, 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 outlet of vaporizer (3) is connected on pressure vessel
Entrance, the outlet of high-pressure heater shunt valve (2) is connected on the second entrance of vaporizer (3)；
Working medium in pressure vessel (6) is driven by the Power Drive Unit in pressure vessel (6), comes for pressurized-water reactor nuclear power plant
Saying, its working medium is demineralized water, and driving means is main pump, and for HTGR Nuclear Power Plant, its working medium is helium, drives dress
It is set to Helium fan；Vaporizer (3) is shell-and-tube heat exchanger, and shell-side is the primary side of vaporizer (3), and tube side is vaporizer (3)
Secondary side, the first entrance of vaporizer (3) accesses the primary side of vaporizer (3), and the first outlet of vaporizer (3) is for vaporizer
(3) primary side outlet, the second entrance of vaporizer (3) accesses the secondary side entrance of vaporizer (3), the secondary of vaporizer (3)
Side outlet is connected on the 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), connects drain valve on the live steam piping that main inlet throttle-stop valve (4) is front
Door (7).
The system utilizing external steam lifting one loop of nuclear power station temperature to carry out heat examination the most according to claim 1, it is special
Levying and be, external steam is filled with valve group (5) and includes against filling non-return flap, regulation door and the cut-off gate that vapour direction is sequentially connected with.
The system utilizing external steam lifting one loop of nuclear power station temperature to carry out heat examination the most according to claim 1, it is special
Levy and be, before hydrophobic valve (7) includes main inlet throttle-stop valve (4), all hydrophobic on the secondary circuit after feed pump outlet isolating door (1)
Valve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201620666893.8U CN205789136U (en) | 2016-06-28 | 2016-06-28 | Utilize external steam to promote one loop of nuclear power station temperature and carry out the system of heat examination |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201620666893.8U CN205789136U (en) | 2016-06-28 | 2016-06-28 | 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 | Publication Date |
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| CN205789136U true CN205789136U (en) | 2016-12-07 |
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| CN201620666893.8U Active CN205789136U (en) | 2016-06-28 | 2016-06-28 | Utilize external steam to promote one loop of nuclear power station temperature and carry out the system of heat examination |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105957570A (en) * | 2016-06-28 | 2016-09-21 | 西安热工研究院有限公司 | System and method for carrying out hot test by utilizing external steam to raise temperature of primary circuit of nuclear power plant |
| CN106782720A (en) * | 2017-02-28 | 2017-05-31 | 西安热工研究院有限公司 | A kind of utilization auxiliary steam heating and the system and method for cooling start and stop heaping equipment |
| CN113123836A (en) * | 2019-12-30 | 2021-07-16 | 上海电气电站设备有限公司 | Back pressure steam turbine starting method |
| 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 |
-
2016
- 2016-06-28 CN CN201620666893.8U patent/CN205789136U/en active Active
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105957570A (en) * | 2016-06-28 | 2016-09-21 | 西安热工研究院有限公司 | System and method for carrying out hot test by utilizing external steam to raise temperature of primary circuit of nuclear power plant |
| CN106782720A (en) * | 2017-02-28 | 2017-05-31 | 西安热工研究院有限公司 | A kind of utilization auxiliary steam heating and the system and method for cooling start and stop heaping equipment |
| CN113123836A (en) * | 2019-12-30 | 2021-07-16 | 上海电气电站设备有限公司 | Back pressure steam turbine starting method |
| CN113123836B (en) * | 2019-12-30 | 2022-07-19 | 上海电气电站设备有限公司 | Back pressure steam turbine starting method |
| 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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| GR01 | Patent grant |