CN105945014B - A kind of system and method for nuclear power station main steam line steam blowing - Google Patents
A kind of system and method for nuclear power station main steam line steam blowing Download PDFInfo
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- CN105945014B CN105945014B CN201610494465.6A CN201610494465A CN105945014B CN 105945014 B CN105945014 B CN 105945014B CN 201610494465 A CN201610494465 A CN 201610494465A CN 105945014 B CN105945014 B CN 105945014B
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- 238000007664 blowing Methods 0.000 title claims abstract description 35
- 238000000034 method Methods 0.000 title claims abstract description 31
- 238000010926 purge Methods 0.000 claims description 20
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 19
- 238000010438 heat treatment Methods 0.000 claims description 13
- 238000002955 isolation Methods 0.000 claims description 10
- 239000007789 gas Substances 0.000 claims description 8
- 230000003584 silencer Effects 0.000 claims description 7
- 239000001307 helium Substances 0.000 claims description 6
- 229910052734 helium Inorganic materials 0.000 claims description 6
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical group [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims description 6
- 230000008878 coupling Effects 0.000 claims description 3
- 238000010168 coupling process Methods 0.000 claims description 3
- 238000005859 coupling reaction Methods 0.000 claims description 3
- 230000001105 regulatory effect Effects 0.000 claims description 2
- 230000000630 rising effect Effects 0.000 claims description 2
- 238000005406 washing Methods 0.000 abstract description 3
- 238000009434 installation Methods 0.000 abstract 1
- 230000000694 effects Effects 0.000 description 3
- 238000011010 flushing procedure Methods 0.000 description 2
- 230000003749 cleanliness Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000009834 vaporization Methods 0.000 description 1
- 230000008016 vaporization Effects 0.000 description 1
Classifications
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B08—CLEANING
- B08B—CLEANING IN GENERAL; PREVENTION OF FOULING IN GENERAL
- B08B9/00—Cleaning hollow articles by methods or apparatus specially adapted thereto
- B08B9/02—Cleaning pipes or tubes or systems of pipes or tubes
- B08B9/027—Cleaning the internal surfaces; Removal of blockages
- B08B9/032—Cleaning the internal surfaces; Removal of blockages by the mechanical action of a moving fluid, e.g. by flushing
- B08B9/0321—Cleaning the internal surfaces; Removal of blockages by the mechanical action of a moving fluid, e.g. by flushing using pressurised, pulsating or purging fluid
- B08B9/0328—Cleaning the internal surfaces; Removal of blockages by the mechanical action of a moving fluid, e.g. by flushing using pressurised, pulsating or purging fluid by purging the pipe with a gas or a mixture of gas and liquid
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- Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- Control Of Turbines (AREA)
- Engine Equipment That Uses Special Cycles (AREA)
Abstract
The invention discloses a kind of system and method for nuclear power station main steam line steam blowing, valve group (8) is filled with including feedwater pump discharge isolating door (1), high-pressure heater shunt valve (2) and external steam, wherein, the outlet of feedwater pump discharge isolating door (1) is connected to the entrance of high-pressure heater shunt valve (2), and perforate installation external steam is filled with valve group (8) on the feedwater piping after feedwater pump discharge isolating door (1).The time that external steam is heated to the steam needs of steam blow parameters using heat caused by main pump (main core blower fan) rotation by the inventive method is shorter, greatly shortens the washing pipe time, reduces the test run duration.
Description
The technical field is as follows:
the invention relates to the technical field of nuclear power, in particular to a system and a method for steam purging of a main steam pipeline of a nuclear power station.
Background art:
the current purging method adopted by a main steam pipeline of a pressurized water reactor nuclear power plant comprises the following steps:
(1) the water is heated by the friction heat generated by the rotation of the main pump of the nuclear island during the heat test to be changed into steam, and the steam blowpipes are used. Because the heat generated by the main pump is limited and the latent heat of water vaporization is very large, the time for generating steam is very long, the steam quantity is very small, the time for blowing the pipe is very long, and the pipe can only be used for blowing symbolically, thus the requirement of blowing the pipe cannot be met;
(2) compressed air is blown through the lance. The method has the advantages that the GB50235 requires that the steam pipeline is blown by the steam pipeline, the compressed air blowing pipe is utilized, the requirement of GB50235 is not met, and the blowing effect is not good without temperature alternation in the blowing process;
steam parameters of the high-temperature gas cooled reactor are much higher than those of a pressurized water reactor, the requirement on the cleanliness of a pipeline is stricter, and no proper method exists at present.
The invention content is as follows:
the invention aims to provide a system and a method for steam purging of a main steam pipeline of a nuclear power station, which are suitable for a pressurized water reactor nuclear power station and a high-temperature gas-cooled reactor nuclear power station, aiming at the problems that the existing method for purging the main steam pipeline of the secondary loop of the pressurized water reactor nuclear power station is insufficient and no suitable method is available for the main steam pipeline of the secondary loop of the high-temperature gas-cooled reactor.
In order to achieve the purpose, the invention is realized by adopting the following technical scheme:
a steam purging system for a main steam pipeline of a nuclear power station comprises a feed pump outlet isolation door, a high-pressure heater bypass pipe and an external steam charging valve group, wherein,
the outlet of the water-feeding pump outlet isolation door is connected with the inlet of the high-pressure heater bypass pipe, and an opening is arranged on a water-feeding pipeline behind the water-feeding pump outlet isolation door and is provided with an external steam charging valve group.
The invention is further improved in that the external steam charging valve group comprises a check valve, an adjusting valve and a stop valve which are connected in sequence against the steam charging direction.
The invention further improves that the invention also comprises an evaporator and a pressure container; wherein,
the outlet of the pressure container is connected with the first inlet of the evaporator, the first outlet of the evaporator is connected with the inlet of the pressure container, and the outlet of the high-pressure heater bypass pipe is connected with the second inlet of the evaporator; the evaporator is a shell-and-tube heat exchanger, the shell side is the primary side of the evaporator, the tube side is the secondary side of the evaporator, a first inlet of the evaporator is connected to the primary side of the evaporator, a first outlet of the evaporator is a primary side outlet of the evaporator, a second inlet of the evaporator is connected to a secondary side inlet of the evaporator, and a secondary side outlet of the evaporator is connected to a second outlet of the evaporator; the system connected to the primary side of the evaporator becomes a primary circuit, and the system connected to the secondary side of the evaporator becomes a secondary circuit.
The invention is further improved in that the working medium in the pressure container is driven by a power driving device in the pressure container, wherein for a pressurized water reactor nuclear power plant, the working medium is desalted water, the driving device is a main pump, for a high temperature gas cooled reactor nuclear power plant, the working medium is helium, and the driving device is a main helium fan.
The invention has the further improvement that the invention also comprises a main throttle valve, a blow pipe temporary control valve and a silencer; wherein,
the inlet of the main throttle valve is connected with the second outlet of the evaporator; the export of main valve adopts the false door core that the steam turbine factory provided to plug up, and gets main valve door pole and fall to through the entry of interim union coupling at interim blowpipe control gate, the entry of muffler is connected to the export of interim blowpipe control gate.
The invention is further improved in that the bypass pipe of the high-pressure heater, the secondary side of the evaporator and the front of the main valve are provided with drain valves which are collectively called two-loop drain valves.
A method for steam purging of a main steam pipeline of a nuclear power station comprises the following steps:
1) closing an isolating door of a feed pump outlet, opening a two-loop drain valve, and slightly opening a temporary blow pipe control door by 5%;
2) external steam is filled into the bypass pipe of the high-pressure heater and the secondary side of the evaporator through an external steam filling valve group until the main throttle valve and the temporary blow pipe control valve, and a small amount of steam is discharged into the atmosphere through the temporary blow pipe control valve and the silencer;
3) in the steam charging process, the charging speed of the steam is controlled by charging external steam into a regulating valve in a valve group, so that the steam charging is ensured to be smooth, water impact is avoided, and the temperature rise speed of the evaporator is ensured to be smaller than the temperature rise limit value;
4) when the steam discharged from the temporary blow pipe control door does not carry water, the temporary blow pipe control door and the two-loop drain valve are closed, then the pressure and the temperature of the two loops are slowly increased, and the temperature increasing and pressure increasing speed of the evaporator is ensured to be smaller than the temperature and pressure limit values in the temperature increasing and pressure increasing processes;
5) starting a power driving device in the pressure container, enabling a primary loop working medium to circularly flow through the rotation of the driving device, enabling the primary loop working medium to absorb the heat of the steam of the secondary loop, slowly raising the temperature, and further heating the working medium of the primary loop by the friction heat of the driving device;
6) with the pressure and temperature of the two loops rising, when the steam pressure of the two loops is equal to the external steam pressure, the external steam can not be charged into the two loops again;
7) under the heating of heat generated by the rotary friction of the evaporator power driving device, the temperature and the pressure of a primary loop working medium are further increased, meanwhile, the heat is transferred to a secondary loop, the steam of the secondary loop is further heated, so that the steam pressure and the temperature of the secondary loop are further increased, and when the steam pressure of the secondary loop is higher than the external steam pressure, the external steam is charged into a check valve in a valve group to be automatically closed;
8) when the temperature and the pressure of steam in the two loops meet the requirement of a blowing pipe, opening a blowing pipe of a temporary control door of the blowing pipe;
9) in the process of blowing the pipe, the pressure of the two loops is reduced, when the pressure of the two loops is lower than the external steam pressure, the check valve filled in the valve group by the external steam is automatically opened, the external steam is filled in the two loops, and when the temperature of the steam of the two loops is close to the temperature of the external steam, the temporary blowing pipe control door is closed;
10) the above processes 6) to 9) are repeated until the system is purged.
The invention is further improved in that the external steam is start-up boiler steam, heating boiler steam or neighbor auxiliary steam.
Compared with the prior art, the invention has the following advantages:
the steam purging system and the steam purging method for the main steam pipeline of the nuclear power station have the following obvious advantages:
1. the time for heating external steam to steam with blowing pipe parameters is shorter by utilizing the heat generated by the rotation of a main pump (a main nuclear fan), so that the pipe washing time is greatly shortened, and the trial run period is shortened;
2. the temperature of the steam in the blowing pipe is higher, and the blowing effect is better;
3. the problem that the main steam pipeline of the high-temperature gas cooled reactor cannot be blown is solved.
4. The system mainly utilizes the original equipment of the nuclear power station, and has less additional equipment and low investment cost.
Compared with the currently used method, the method has the following obvious advantages:
1. the time for heating external steam to steam with blowing pipe parameters is shorter by utilizing the heat generated by the rotation of a main pump (a main nuclear fan), so that the pipe washing time is greatly shortened, and the trial run period is shortened;
2. the temperature of the steam in the blowing pipe is higher, and the blowing effect is better;
3. the problem that the main steam pipeline of the high-temperature gas cooled reactor cannot be blown is solved.
Description of the drawings:
FIG. 1 is a block diagram of a steam purging system for a main steam pipeline of a nuclear power plant according to the present invention.
The specific implementation mode is as follows:
the invention is further described below with reference to the accompanying drawings.
As shown in fig. 1, the steam purging system for the main steam pipeline of the nuclear power station provided by the invention comprises a feed pump outlet isolation door 1, a high-pressure heater bypass pipe 2, an evaporator 3, a main steam valve 4, a silencer 5, a blow pipe temporary control door 6, a pressure vessel 7 and an external steam filling valve group 8, wherein the outlet of the feed pump outlet isolation door 1 is connected with the inlet of the high-pressure heater bypass pipe 2, and the external steam filling valve group 8 is arranged on an opening of the feed pipe behind the feed pump outlet isolation door 1; the outlet of the pressure container 7 is connected with the first inlet of the evaporator 3, the first outlet of the evaporator 3 is connected with the inlet of the pressure container 7, and the outlet of the high-pressure heater bypass pipe 2 is connected with the second inlet of the evaporator 3; the evaporator 3 is a shell-and-tube heat exchanger, the shell side is the primary side of the evaporator 3, the tube side is the secondary side of the evaporator 3, a first inlet of the evaporator 3 is connected to the primary side of the evaporator 3, a first outlet of the evaporator 3 is the primary side outlet of the evaporator 3, a second inlet of the evaporator 3 is connected to the secondary side inlet of the evaporator 3, and a secondary side outlet of the evaporator 3 is connected to the second outlet of the evaporator 3; the inlet of the main valve 4 is connected with the second outlet of the evaporator 3; the export of main valve 4 adopts the false door core that the steam turbine factory provided to plug up, and main valve door pole gets off to through interim union coupling at the entry of interim blowpipe control gate 6, the entry of muffler 5 is connected to the export of interim blowpipe control gate 6.
The external steam charging valve group 8 comprises a check valve, an adjusting valve and a stop valve which are connected in sequence. The working medium in the pressure container 7 is driven by a power driving device in the pressure container 7, wherein for a pressurized water reactor nuclear power plant, the working medium is desalted water, the driving device is a main pump, for a high temperature gas cooled reactor nuclear power plant, the working medium is helium gas, and the driving device is a helium main fan.
The invention provides a steam purging method for a main steam pipeline of a nuclear power station, which specifically comprises the following steps:
1) the auxiliary steam turbine main valve rod is connected with a temporary pipeline, is connected with a temporary blow pipe control valve, and is connected with a silencer through the temporary pipeline;
2) the outlet valve of the feed pump is tightly closed, a temporary three-way pipe is connected behind the outlet valve of the feed pump, and a temporary steam filling valve is installed;
3) filling steam into the high water adding system, the secondary loop of the steam generator and the main steam system by using external steam (starting a boiler, a heating boiler, adjacent auxiliary steam and the like);
4) the heat generated by the rotation of a primary loop main pump (a main nuclear fan) of the nuclear power station is utilized to heat the steam of the secondary loop through an evaporator, so that the temperature of the steam in the system is further raised, and the pressure is further increased;
5) when the temperature and the pressure of steam in the two loops meet the requirement of a blowing pipe, opening a blowing pipe of a temporary control door of the blowing pipe;
6) the above process is repeated until the system is purged.
The following description will be given of a specific embodiment of the invention by taking a system for purging a main steam pipeline of a certain nuclear power unit as an example.
The external steam source available for the unit comprises 1 electric boiler capable of generating steam with 42t/h parameter of 1.25MPa and 193 ℃ and 5 coal-fired boilers capable of generating steam with 10t/h parameter of 1.25MPa and 193 ℃. The total steam production is 92 t/h. The power of a main pump (a main nuclear fan) of the unit is 4500 KW.
1) The auxiliary steam turbine main valve rod is connected with a temporary pipeline, is connected with a temporary blow pipe control valve, and is connected with a silencer through the temporary pipeline;
2) tightly closing a water supply pump outlet valve, connecting a temporary three-way pipe behind the water supply pump outlet valve, and installing a temporary steam charging valve group, wherein the temporary valve group comprises a check valve, an adjusting valve and a stop valve;
3) filling steam into the high pressure bypass pipeline, the secondary loop of the steam generator and the main steam system by using external steam (starting a boiler, a heating boiler, adjacent auxiliary steam and the like);
4) and (3) heating the pipeline used by the blowing pipe in the steam charging process, and closing all the drainage and steam exhaust valves after the heating is finished to start boosting. And when the pressure in the two-loop system reaches 1.0MPa, opening the temporary pipe flushing valve for trial blowing, and recording the pressure of the steam outlet in the trial blowing process, wherein the pressure of the steam outlet plus the resistance of the main steam pipeline under the rated working condition is the formal blowing pipe pressure. Since the pressure at the exhaust port of the plant was 0.5MPa, the pressure at the main blow pipe was determined to be 2.7MPa or more.
5) After the trial blowing is finished, the temporary blowing pipe door is closed, and the system continues to boost pressure. When the pressure of the system reaches 1.25MPa, the non-return valve is closed, and steam charging is stopped;
6) starting a main pump (a main nuclear fan), and heating the steam of the two loops through an evaporator by using heat generated by the rotation friction of the main pump (the main nuclear fan), so that the temperature of the steam in the system is further increased, and the pressure is further increased;
7) when the steam pressure at the outlet of the evaporator reaches 3.5MPa, opening a temporary control door blowpipe of the blowpipe, and when the pressure of the system is lower than the external steam supply pressure, opening a check valve and refilling the system. When the temperature of the outlet of the evaporator reaches about 200 ℃, the temporary pipe flushing door is closed, the system is boosted, and when the pressure of the system is more than 1.25MPa, the check valve is closed. The system is heated by heat generated by the rotary friction of a main pump (a main nuclear fan), and the pressure and the temperature are further increased until the pressure reaches 3.5 MPa.
8) The above process is repeated until the system is purged.
Claims (7)
1. A steam purging system for a main steam pipeline of a nuclear power station is characterized by comprising a feed pump outlet isolation door (1), a high-pressure heater bypass pipe (2) and an external steam filling valve group (8), wherein,
the outlet of the feed pump outlet isolation door (1) is connected with the inlet of the high-pressure heater bypass pipe (2), and an external steam charging valve group (8) is arranged on an opening of a feed pipe behind the feed pump outlet isolation door (1);
the device also comprises an evaporator (3) and a pressure container (7); wherein,
the outlet of the pressure container (7) is connected with the first inlet of the evaporator (3), the first outlet of the evaporator (3) is connected with the inlet of the pressure container (7), and the outlet of the high-pressure heater bypass pipe (2) is connected with the second inlet of the evaporator (3); the evaporator (3) is a shell-and-tube heat exchanger, the shell side is the primary side of the evaporator (3), the tube side is the secondary side of the evaporator (3), a first inlet of the evaporator (3) is connected to the primary side of the evaporator (3), a first outlet of the evaporator (3) is a primary side outlet of the evaporator (3), a second inlet of the evaporator (3) is connected to a secondary side inlet of the evaporator (3), and a secondary side outlet of the evaporator (3) is connected to a second outlet of the evaporator (3); a system connected to the primary side of the evaporator (3) is a primary circuit, and a system connected to the secondary side of the evaporator (3) is a secondary circuit.
2. The system for steam purging of a main steam pipeline of a nuclear power plant as claimed in claim 1, wherein the external steam charging valve group (8) comprises a check valve, an adjusting valve and a stop valve which are connected in sequence against the steam charging direction.
3. The system for steam purging of the main steam pipeline of the nuclear power station according to claim 1, wherein a working medium in the pressure vessel (7) is driven by a power driving device in the pressure vessel (7), wherein the working medium is desalted water for a pressurized water reactor nuclear power station, the driving device is a main pump, the working medium is helium gas for a high temperature gas cooled reactor nuclear power station, and the driving device is a main helium fan.
4. The system for steam purging of the main steam pipeline of the nuclear power plant as claimed in claim 1, further comprising a main throttle (4), a blow pipe temporary control door (6) and a silencer (5); wherein,
the inlet of the main throttle valve (4) is connected with the second outlet of the evaporator (3); the export of main steam valve (4) adopts the false door core that the steam turbine factory provided to block up, and gets main steam valve lever off to through interim union coupling in the entry of interim blowpipe control gate (6), the entry of muffler (5) is connected to the export of interim blowpipe control gate (6).
5. The system for steam purging of the main steam pipeline of the nuclear power plant as claimed in claim 1, wherein the bypass pipe (2) of the high-pressure heater, the secondary side of the evaporator (3) and the front of the main steam valve (4) are provided with drain valves, and the drain valves are collectively called two-loop drain valves.
6. A method for steam purging of a main steam pipeline of a nuclear power station is characterized by comprising the following steps:
1) tightly closing an outlet isolation door (1) of the feed pump, opening a two-loop drain valve, and slightly opening a temporary blow pipe control door (6) by 5%;
2) external steam is filled into the bypass pipe (2) of the high-pressure heater and the secondary side of the evaporator (3) to the front of the main throttle valve (4) and the temporary blowing pipe control door (6) through an external steam filling valve group (8), and a small amount of steam is discharged into the atmosphere through the temporary blowing pipe control door (6) and the silencer (5);
3) the steam charging speed is controlled by the regulating valve in the external steam charging valve group (8) in the steam charging process, so that the steam charging is smooth, the water impact is avoided, and the temperature rise speed of the evaporator (3) is smaller than the temperature rise limit value;
4) when the steam discharged from the temporary blow pipe control door (6) does not carry water, the temporary blow pipe control door (6) and the two-loop drain valve are closed, then the pressure and the temperature of the two loops slowly rise, and the temperature rise and the pressure rise speed of the evaporator (3) are ensured to be smaller than the temperature and pressure limit values in the temperature rise and pressure rise processes;
5) starting a power driving device in the pressure container (7), enabling a primary circuit working medium to circularly flow through the rotation of the driving device, absorbing the heat of the steam of the secondary circuit by the primary circuit working medium, slowly raising the temperature, and further heating the working medium of the primary circuit by the friction heat of the driving device;
6) with the pressure and temperature of the two loops rising, when the steam pressure of the two loops is equal to the external steam pressure, the external steam can not be charged into the two loops again;
7) under the heating of heat generated by the rotation friction of the power driving device of the evaporator (3), the temperature and the pressure of a primary circuit working medium are further increased, and simultaneously, the heat is transferred to the secondary circuit to further heat the steam of the secondary circuit, so that the steam pressure and the temperature of the secondary circuit are further increased, and when the steam pressure of the secondary circuit is higher than the external steam pressure, the external steam is filled into a check valve in a valve group (8) to be automatically closed;
8) when the temperature and the pressure of steam in the two loops meet the requirement of a blowing pipe, opening a blowing pipe of a temporary control door of the blowing pipe;
9) in the process of blowing the pipe, the pressure of the two loops is reduced, when the pressure of the two loops is lower than the external steam pressure, the check valve filled in the valve group (8) by the external steam is automatically opened, the external steam is filled in the two loops, and when the temperature of the steam of the two loops is close to the temperature of the external steam, the temporary blowing pipe control door (6) is closed;
10) the above processes 6) to 9) are repeated until the system is purged.
7. The method for steam purging of the main steam pipeline of the nuclear power plant as recited in claim 6, wherein the external steam is start-up boiler steam, heating boiler steam or adjacent auxiliary steam.
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| CN201610494465.6A CN105945014B (en) | 2016-06-28 | 2016-06-28 | A kind of system and method for nuclear power station main steam line steam blowing |
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| CN201610494465.6A CN105945014B (en) | 2016-06-28 | 2016-06-28 | A kind of system and method for nuclear power station main steam line steam blowing |
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| CN105945014B true CN105945014B (en) | 2018-02-16 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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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 |
| CN107150055A (en) * | 2017-07-04 | 2017-09-12 | 山东中实易通集团有限公司 | The auxiliary vapour purging system and method not restricted before a kind of unit starting by steam |
| CN108435719B (en) * | 2018-02-06 | 2020-05-12 | 华电电力科学研究院有限公司 | Method for purging long-distance steam pipeline in extremely cold region |
| 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 |
| 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 |
| CN111677966A (en) * | 2020-05-28 | 2020-09-18 | 清华大学 | Pipeline communication device for high-temperature gas cooled reactor |
| CN113819453B (en) * | 2021-10-28 | 2023-04-28 | 华能山东石岛湾核电有限公司 | Device and method for improving water supply temperature in high-temperature gas cooled reactor starting stage |
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