CN207776920U - A kind of system of nuclear power generating sets vapor self - Google Patents
A kind of system of nuclear power generating sets vapor self Download PDFInfo
- Publication number
- CN207776920U CN207776920U CN201820140559.8U CN201820140559U CN207776920U CN 207776920 U CN207776920 U CN 207776920U CN 201820140559 U CN201820140559 U CN 201820140559U CN 207776920 U CN207776920 U CN 207776920U
- Authority
- CN
- China
- Prior art keywords
- steam
- auxiliary vapour
- entrance
- outlet
- auxiliary
- 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.)
- Active
Links
Landscapes
- Control Of Turbines (AREA)
- Control Of Steam Boilers And Waste-Gas Boilers (AREA)
Abstract
The utility model discloses a kind of systems of nuclear power generating sets vapor self, the system includes auxiliary vapour header, steam turbine, condenser, bypass valve, evaporator, water supply system, external steam-supplying system, auxiliary vapour user and auxiliary vapour valve group, when work, the utility model includes the following steps：1) before reactor start-up, from external steam-supplying system to auxiliary vapour header steam supply；2) after reactor start-up and reactor export generate steam, steam is controlled by bypassing into auxiliary vapour header by the regulating valve in auxiliary vapour valve group, external steam-supplying system is reduced simultaneously to auxiliary vapour header evaporation capacity for engine, until the steam supply of external steam-supplying system is cut off completely；3) it from the steam extraction of steam turbine to auxiliary vapour header steam supply after steam turbine on-load, gradually cuts off from the bypass duct before bypass valve to the steam supply of auxiliary vapour header；4) after steam turbine tripping, restore from bypass to the steam supply of auxiliary vapour header.
Description
Technical field
The utility model belongs to technical field of nuclear power, and in particular to a kind of system of nuclear power generating sets vapor self.
Background technology
The main vapour source of HTGR Nuclear Power Plant auxiliary vapour at present is extracted steam from turbine, and standby steam source is that electric boiler generates
Steam.
System is primarily present following deficiency at present：
1) before the non-on-load of steam turbine, steam extraction can not obtain, and evaporator feedwater can only be by electric boiler to deoxygenation
Device steam supply heats, and electric boiler needs long-play, costly, heating effect is poor and unstable；
2) unit is in initial start stage, and a large amount of steam to condenser, are discharged into the steam of condenser by the row of bypass, heat without
Method is utilized, and is the waste of energy；
3) steam is discharged into condenser, improves the temperature of condensed water, reduces the efficiency of steam turbine；
4) the excessively high operation that can influence precision processing of the temperature of condensed water；
5) steam enters after condenser becomes condensed water, also to squeeze into oxygen-eliminating device using condensate pump, increase condensed water
The wasted work of pump；
6) when shutting down not shutdown operating condition, after halt turbines, steam extraction all loses, and auxiliary vapour header loses vapour
Source needs electric boiler to restore steam supply, therefore in unit normal operation, and electric boiler needs to be in hot stand-by duty, is energy
Waste；
7) even if electric boiler is in hot stand-by duty, but can be needed at least effectively to auxiliary vapour header steam supply from hot standby use
15 minutes or more, this period of vapour source is lost in auxiliary vapour header, oxygen-eliminating device loses heating, and axle envelope loses vapour source, pacifies to unit
Row for the national games and further startup impact.
Utility model content
The purpose of this utility model is that for the deficiency of current machine set system, a kind of nuclear power generating sets vapor self is provided
System.
In order to achieve the above objectives, what the utility model adopts the following technical solution to realize：
A kind of system of nuclear power generating sets vapor self, including auxiliary vapour header, steam turbine, bypass valve, external steam-supplying system,
Auxiliary vapour user and auxiliary vapour valve group；Wherein,
Reject steam pipeline upper connector road before bypass valve to auxiliary vapour valve group entrance, auxiliary vapour valve group
Outlet connects the first entrance of auxiliary vapour header, and the second entrance of auxiliary vapour header is connected on the first outlet of steam turbine, and the of auxiliary vapour header
Three entrances are connected on the outlet of external steam-supplying system, and the outlet of auxiliary vapour header is connected on the entrance of auxiliary vapour user.
The utility model, which further improves, to be, further includes condenser, evaporator and water supply system；Wherein,
The outlet of evaporator is divided into two strands, and first strand of entrance for being connected on steam turbine, second strand is connected on entering for bypass valve
Mouthful；The second outlet of steam turbine is connected on the first entrance of condenser；The outlet of bypass valve is connected on the second entrance of condenser；
The outlet of condenser is connected on the entrance of water supply system；The outlet of water supply system is connected on the entrance of evaporator.
The utility model, which further improves, to be, auxiliary vapour valve group is bypass valve preceding pipeline to auxiliary vapour header entrance
Cut-off gate and adjust door.
The utility model, which further improves, to be, auxiliary vapour user includes oxygen-eliminating device heating vapour user and turbine shaft seal
With vapour user.
The utility model, which further improves, to be, the first outlet of steam turbine is the steam extraction of steam turbine.
The utility model provides a kind of system of nuclear power generating sets vapor self, and system usually used at present compared with
Lower several respects clear advantage：
1) heat of partial bypass steam has directly been recycled, there is energy-saving effect；
2), to after auxiliary vapour header steam supply, electric boiler can be out of service using reject steam, there is energy-efficient effect；
3) in unit normal operation, electric boiler can switch to cold standby state from hot stand-by duty, have energy-efficient effect
Fruit；
4) after steam turbine tripping, auxiliary vapour header can restore steam supply within a very short time, be conducive to the peace of nuclear power generating sets
Entirely, stable operation；
5) temperature for reducing startup stage condensed water improves the efficiency of steam turbine；
6) temperature for reducing startup stage condensed water is advantageous to the safe operation of precision processing system；
7) output for reducing solidifying pump, has energy-saving effect.
Description of the drawings
Fig. 1 is a kind of structure diagram of the system of nuclear power generating sets vapor self of the utility model.
In figure：The auxiliary vapour headers of 1-, 2- steam turbines, 3- condensers, 4- bypass valves, 5- evaporators, 6- water supply systems, 7-
External steam-supplying system, the auxiliary vapour users of 8-, the auxiliary vapour valve groups of 9-.
Specific implementation mode
The utility model is further described in detail below in conjunction with attached drawing.
As shown in Figure 1, a kind of system of nuclear power generating sets vapor self provided by the utility model, including auxiliary vapour header 1, steamer
Machine 2, bypass valve 4, external steam-supplying system 7, auxiliary vapour user 8, auxiliary vapour valve group 9；Wherein, the side before bypass valve 4
To the entrance of auxiliary vapour valve group 9, the outlet of auxiliary vapour valve group 9 connects the first of auxiliary vapour header 1 and enters in road jet chimney upper connector road
Mouthful, the second entrance of auxiliary vapour header 1 is connected on the first outlet of steam turbine 2, and the third entrance of auxiliary vapour header 1 is connected on external steam supply system
The outlet of system 7, the outlet of auxiliary vapour header 1 is connected on the entrance of auxiliary vapour user 8.
In addition, the utility model further includes condenser 3, evaporator 5 and water supply system 6；Wherein, the outlet of evaporator 5 point
It is two strands, first strand of entrance for being connected on steam turbine 2, second strand of entrance for being connected on bypass valve 4；The second outlet of steam turbine 2
It is connected on the first entrance of condenser 3；The outlet of bypass valve 4 is connected on the second entrance of condenser 3；The outlet of condenser 3 connects
In the entrance of water supply system 6；The outlet of water supply system 6 is connected on the entrance of evaporator 5.
Wherein, auxiliary vapour valve group 9 is 4 preceding pipeline of bypass valve to the cut-off gate of auxiliary 1 entrance of vapour header and adjusts door.It is auxiliary
Vapour user 8 includes that the nuclear power stations such as oxygen-eliminating device heating vapour, turbine shaft seal vapour need to use all users of vapour.Steam turbine 2
Second outlet is the steam extraction of steam turbine.
When work, the utility model includes the following steps：
1) before reactor start-up, from external steam-supplying system 7 to auxiliary 1 steam supply of vapour header, auxiliary vapour user 8 is from auxiliary vapour header 1
Take vapour；
2) after reactor start-up and reactor export generate steam, steam is discharged into condenser 3 by bypass valve 4,
Its upstream pressure is adjusted by bypass valve 4 at this time and is higher than auxiliary 1 pressure of vapour header, and passes through the adjusting in auxiliary vapour valve group 9
Valve controls steam by bypassing into auxiliary vapour header 1, while reducing external steam-supplying system 7 to auxiliary 1 evaporation capacity for engine of vapour header, until will be outer
The steam supply of portion's steam-supplying system 7 is cut off completely；
3) after 2 on-load of steam turbine, extraction pressure higher than auxiliary vapour header 1 pressure after, from the steam extraction of steam turbine 2 to
Auxiliary 1 steam supply of vapour header is gradually cut off from the bypass duct before bypass valve 4 to the steam supply of auxiliary 1 steam supply of vapour header；
4) after the tripping of steam turbine 2, the steam extraction of steam turbine 2 is lost, and restores at this time by the bypass duct before bypass valve 4
To the steam supply of auxiliary 1 steam supply of vapour header.
Claims (5)
1. a kind of system of nuclear power generating sets vapor self, which is characterized in that adjusted including auxiliary vapour header (1), steam turbine (2), bypass
Valve (4), external steam-supplying system (7), auxiliary vapour user (8) and auxiliary vapour valve group (9)；Wherein,
Reject steam pipeline upper connector road before bypass valve (4) is to the entrance of auxiliary vapour valve group (9), auxiliary vapour valve group
(9) outlet connects the first entrance of auxiliary vapour header (1), and the second entrance of auxiliary vapour header (1) is connected on the first of steam turbine (2) and goes out
Mouthful, the third entrance of auxiliary vapour header (1) is connected on the outlet of external steam-supplying system (7), and the outlet of auxiliary vapour header (1) is connected on auxiliary vapour and uses
The entrance at family (8).
2. a kind of system of nuclear power generating sets vapor self according to claim 1, which is characterized in that further include condenser (3),
Evaporator (5) and water supply system (6)；Wherein,
The outlet of evaporator (5) is divided into two strands, and first strand of entrance for being connected on steam turbine (2), second strand is connected on bypass valve (4)
Entrance；The second outlet of steam turbine (2) is connected on the first entrance of condenser (3)；The outlet of bypass valve (4) is connected on condensing
The second entrance of device (3)；The outlet of condenser (3) is connected on the entrance of water supply system (6)；The outlet of water supply system (6) is connected on steaming
Send out the entrance of device (5).
3. a kind of system of nuclear power generating sets vapor self according to claim 1, which is characterized in that auxiliary vapour valve group (9) is
Bypass valve (4) preceding pipeline to auxiliary vapour header (1) entrance cut-off gate and adjust door.
4. a kind of system of nuclear power generating sets vapor self according to claim 1, which is characterized in that auxiliary vapour user (8) includes
Oxygen-eliminating device heating is with vapour user and turbine shaft seal vapour user.
5. a kind of system of nuclear power generating sets vapor self according to claim 1, which is characterized in that the first of steam turbine (2)
Outlet is the steam extraction of steam turbine.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201820140559.8U CN207776920U (en) | 2018-01-26 | 2018-01-26 | A kind of system of nuclear power generating sets vapor self |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201820140559.8U CN207776920U (en) | 2018-01-26 | 2018-01-26 | A kind of system of nuclear power generating sets vapor self |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN207776920U true CN207776920U (en) | 2018-08-28 |
Family
ID=63211155
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201820140559.8U Active CN207776920U (en) | 2018-01-26 | 2018-01-26 | A kind of system of nuclear power generating sets vapor self |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN207776920U (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108167036A (en) * | 2018-01-26 | 2018-06-15 | 西安热工研究院有限公司 | A kind of system and method for nuclear power generating sets vapor self |
| CN110118346A (en) * | 2019-06-10 | 2019-08-13 | 西安热工研究院有限公司 | A kind of system and method for nuclear power starting electric boiler stand-by heat |
| CN113266438A (en) * | 2021-05-18 | 2021-08-17 | 西安热工研究院有限公司 | Operation control system and method based on high-temperature gas cooled reactor |
-
2018
- 2018-01-26 CN CN201820140559.8U patent/CN207776920U/en active Active
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108167036A (en) * | 2018-01-26 | 2018-06-15 | 西安热工研究院有限公司 | A kind of system and method for nuclear power generating sets vapor self |
| CN110118346A (en) * | 2019-06-10 | 2019-08-13 | 西安热工研究院有限公司 | A kind of system and method for nuclear power starting electric boiler stand-by heat |
| CN110118346B (en) * | 2019-06-10 | 2024-01-30 | 西安热工研究院有限公司 | Nuclear power starting electric boiler hot standby system and method |
| CN113266438A (en) * | 2021-05-18 | 2021-08-17 | 西安热工研究院有限公司 | Operation control system and method based on high-temperature gas cooled reactor |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN108167036A (en) | A kind of system and method for nuclear power generating sets vapor self | |
| CN204730303U (en) | The heating system of the 12MW small cogeneration unit under a kind of underrun operating mode | |
| CN208594973U (en) | It is a kind of to combine frequency modulation peak regulation system using electrochemical energy storage coupling condensed water heat accumulation | |
| CN207776920U (en) | A kind of system of nuclear power generating sets vapor self | |
| CN111852597A (en) | Variable-parameter multi-element cascade thermoelectric decoupling system of thermal power heat supply unit and adjusting method | |
| CN106838865B (en) | Completely thermoelectric decoupling steam extraction and heat supply power station system and working method | |
| CN106678770A (en) | System and method for heating feed water of evaporator of nuclear power unit | |
| CN104976671B (en) | Wide-load heat supply energy-saving system of back pressure type small steam turbine driven water feeding pump | |
| CN110131003A (en) | A kind of system and method for high temperature gas cooled reactor nuclear power unit secondary circuit start and stop | |
| CN107559056B (en) | Steam turbine increasing system with AGC function and adjusting method | |
| CN113389606B (en) | Direct heat supply system and method for exhaust steam and extraction steam of medium-pressure cylinder of steam turbine of nuclear power unit | |
| CN210118175U (en) | Pressurized water reactor nuclear power unit two-loop thermodynamic system self-adaptation steam supply system | |
| CN112856363B (en) | System and method for improving heat supply steam parameters of deep peak shaving heat supply unit | |
| CN110397479A (en) | A kind of multivariable collaboration frequency modulation peak regulation system and method | |
| CN112303610A (en) | Operation system and method for recovering high-energy water in shutdown and non-shutdown operation mode | |
| CN103628937B (en) | Method for better utilizing waste gas of turboset | |
| CN208564658U (en) | It is a kind of to combine frequency modulation peak regulation system using electrochemical energy storage coupling water supply heat accumulation | |
| CN110726168A (en) | Steam turbine waste heat maximize utilization system of steam power plant | |
| CN212296519U (en) | Variable-parameter multi-element cascade thermoelectric decoupling system of thermal power heat supply unit | |
| CN106246251B (en) | Combined cycle thermoelectric co-feeding system and its height arrange control method of drawing gas | |
| CN210483828U (en) | Energy-saving power generation and utilization system utilizing exhaust steam waste heat of steam turbine of thermal power plant | |
| CN209279143U (en) | A kind of system promoting unit steam supply ability using reheater increase-volume | |
| CN113280390B (en) | Deep peak regulation heat supply grade improving system and method based on heat pump boosting reheating | |
| CN212508456U (en) | Little steam discharge flow air cooling island system of preventing frostbite based on flue gas waste heat utilization | |
| CN112727556B (en) | Peak regulating system with zero output of low-pressure cylinder, heat storage tank and low-pressure heater coupled |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| GR01 | Patent grant | ||
| GR01 | Patent grant |