CN113990536A - Operation system and method for shutdown transient non-shutdown - Google Patents
Operation system and method for shutdown transient non-shutdown Download PDFInfo
- Publication number
- CN113990536A CN113990536A CN202111258578.3A CN202111258578A CN113990536A CN 113990536 A CN113990536 A CN 113990536A CN 202111258578 A CN202111258578 A CN 202111258578A CN 113990536 A CN113990536 A CN 113990536A
- Authority
- CN
- China
- Prior art keywords
- steam
- generator
- steam turbine
- valve group
- main
- 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.)
- Granted
Links
- 230000001052 transient effect Effects 0.000 title claims abstract description 17
- 238000000034 method Methods 0.000 title claims abstract description 12
- 230000001105 regulatory effect Effects 0.000 claims abstract description 19
- 238000001816 cooling Methods 0.000 claims description 3
- 230000001960 triggered effect Effects 0.000 claims description 3
- 239000002918 waste heat Substances 0.000 claims description 3
- 230000035939 shock Effects 0.000 abstract description 4
- 230000009286 beneficial effect Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000001934 delay Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
- G21D5/04—Reactor and engine not structurally combined
- G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
-
- 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
-
- 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Control Of Turbines (AREA)
Abstract
The invention discloses a system and a method for operating a reactor shutdown transient state without shutdown, which comprises a steam generator, a main steam main pipe, a main steam valve/regulating valve group, a steam turbine, a condenser, a bypass valve group, a bypass pipeline, a generator and a generator outlet circuit breaker, wherein the main steam valve/regulating valve group is connected with the steam turbine; the system and the method can improve the generating capacity, avoid thermal shock at the same time, lead out the heat of the reactor in a real-time manner, and have higher safety.
Description
Technical Field
The invention belongs to the technical field of nuclear power, and relates to a shutdown transient non-shutdown operation system and method.
Background
When the reactor of the current nuclear power unit is in an abnormal shutdown state and the conventional island is available, the conventional island steam turbine automatically shuts down: and closing a main steam valve/adjusting valve of the steam turbine, opening a breaker at the outlet of the generator, and introducing sensible heat of the reactor and residual steam of a steam pipeline into a condenser for cooling through side discharge.
The above-mentioned operation mode has the following disadvantages: firstly, at the moment of closing a main steam valve/adjusting valve of a steam turbine, the pressure of a main steam pipeline is increased steeply, so that pressure impact is caused, an atmospheric release valve and a safety valve on the main steam pipeline are opened accidentally, and the safety is low; secondly, the shutdown of the steam turbine delays the export of the heat of the reactor; thirdly, the sensible heat of the reactor and the high-temperature and high-pressure steam left in the steam pipeline enter a condenser through side discharge to generate thermal shock on the side discharge pipeline and the condenser; fourthly, the reactor is shut down, and meanwhile, the breaker at the outlet of the generator is opened, so that the generated energy is reduced, the economic benefit is reduced, and meanwhile, the impact is generated on a power grid.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and provides a shutdown transient non-shutdown operation system and a shutdown transient non-shutdown operation method, which can improve the power generation capacity, avoid thermal shock, guide out the heat of a reactor in a real-time manner and have higher safety.
In order to achieve the aim, the shutdown transient non-shutdown operation system comprises a steam generator, a main steam main pipe, a main steam valve/regulating valve group, a steam turbine, a condenser, a bypass valve group, a bypass pipeline, a generator and a generator outlet circuit breaker;
the outlet of the steam generator is divided into two paths, wherein one path is communicated with the inlet of the steam turbine through a main steam valve/regulating valve group, the other path is communicated with the inlet of the condenser through a side exhaust valve group, the exhaust port of the steam turbine is communicated with the inlet of the condenser, the output shaft of the steam turbine is connected with the driving shaft of the generator, and the output end of the generator is connected with the power grid through a generator outlet circuit breaker.
The outlet of the steam generator is communicated with the inlet of the steam turbine through a main steam main pipe and a main steam valve/regulating valve group.
The outlet of the steam generator is communicated with the inlet of the condenser through a by-pass valve group and a by-pass pipeline.
The invention relates to a shutdown transient non-shutdown operation method, which comprises the following steps:
when the reactor is shut down transiently, the steam turbine is not interlocked to shut down, a breaker at the outlet of the generator keeps on switching on, the steam turbine and the generator keep on running, steam in a main steam main pipe enters the steam turbine to do work, meanwhile, the steam generator continuously guides out sensible heat and decay heat after the reactor is shut down in a forced circulation mode to generate steam, then the steam turbine is supplied with the main steam main pipe to do work, a bypass exhaust valve group keeps closed, the steam turbine is in a rapid power reduction running state to match the steam generation amount of the steam generator, and a main steam valve/regulating valve group keeps open and gradually regulates the valve to be small so as to gradually reduce the power of the steam turbine;
when the load of the steam turbine is reduced to a preset load, the steam turbine and the generator are triggered to automatically stop, a breaker at the outlet of the generator automatically opens, a main steam valve/regulating valve group automatically closes, a side exhaust valve group automatically opens, and low-temperature and low-pressure steam generated by the waste heat of the reactor in the steam generator enters a condenser through the side exhaust valve group and a side exhaust pipeline to be cooled.
The preset load is 10% of the rated load of the steam turbine.
The invention has the following beneficial effects:
when the system and the method for operating the steam turbine without shutdown in the transient shutdown state are operated specifically, the pressure of the main steam main pipe is obviously reduced after the steam turbine operates for a period of time, at the moment when the main steam valve/the regulating valve group is closed, the pressure fluctuation of the main steam main pipe cannot influence a main steam safety valve and an atmospheric release valve, and the safety is high; the continuous operation of the steam turbine is beneficial to the conduction of the heat of the reactor, so that the temperature and the pressure of steam are obviously reduced, and thermal shock to a side exhaust pipeline and a condenser is small; in addition, the delay opening is carried out through the generator outlet breaker so as to increase the generating capacity, improve the economic benefit and have less influence on the power grid during splitting.
Drawings
FIG. 1 is a schematic structural diagram of the present invention.
Wherein, 1 is a steam generator, 2 is a main steam main pipe, 3 is a main steam valve/regulating valve group, 4 is a steam turbine, 5 is a condenser, 6 is a side exhaust valve group, 7 is a side exhaust pipeline, 8 is a generator, and 9 is a generator outlet circuit breaker.
Detailed Description
In order to make the technical solutions of the present invention better understood, the technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, not all of the embodiments, and are not intended to limit the scope of the present disclosure. Moreover, in the following description, descriptions of well-known structures and techniques are omitted so as to not unnecessarily obscure the concepts of the present disclosure. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
There is shown in the drawings a schematic block diagram of a disclosed embodiment in accordance with the invention. The figures are not drawn to scale, wherein certain details are exaggerated and possibly omitted for clarity of presentation. The shapes of various regions, layers and their relative sizes and positional relationships shown in the drawings are merely exemplary, and deviations may occur in practice due to manufacturing tolerances or technical limitations, and a person skilled in the art may additionally design regions/layers having different shapes, sizes, relative positions, according to actual needs.
Referring to fig. 1, the shutdown transient non-shutdown operation system of the present invention includes a steam generator 1, a main steam main pipe 2, a main steam valve/regulating valve group 3, a steam turbine 4, a condenser 5, a bypass valve group 6, a bypass pipeline 7, a generator 8, and a generator outlet breaker 9;
the outlet of the steam generator 1 is divided into two paths, wherein one path is communicated with the inlet of a steam turbine 4 through a main steam main pipe 2 and a main steam valve/regulating valve group 3, the other path is communicated with the inlet of a condenser 5 through a bypass exhaust valve group 6 and a bypass exhaust pipeline 7, the exhaust port of the steam turbine 4 is communicated with the inlet of the condenser 5, the output shaft of the steam turbine 4 is connected with the driving shaft of a generator 8, and the output end of the generator 8 is connected with a power grid through a generator outlet circuit breaker 9.
The invention relates to a shutdown transient non-shutdown operation method, which comprises the following steps:
when the reactor is shut down for a transient state, the steam turbine 4 is not interlocked and shut down, the generator outlet circuit breaker 9 keeps closed, the steam turbine 4 and the generator 8 keep running continuously, and steam in the main steam main pipe 2 enters the steam turbine 4 to do work. Meanwhile, the steam generator 1 continuously leads out sensible heat and decay heat after reactor shutdown in a forced circulation mode and generates steam, then the steam is supplied to the steam turbine 4 to do work through the main steam main pipe 2, the bypass valve group 6 is kept closed at the moment, the steam turbine 4 is in a fast power reduction operation state to match the steam generation amount of the steam generator 1, and the main steam valve/regulating valve group 3 is kept open and gradually regulated to be reduced so as to reduce the power of the steam turbine 4.
When the load of the steam turbine 4 is reduced to 10%, the steam turbine 4 and the generator 8 are triggered to automatically stop, the generator outlet circuit breaker 9 automatically opens, the main steam valve/regulating valve group 3 automatically closes, the bypass exhaust valve group 6 automatically opens, and low-temperature and low-pressure steam generated by reactor waste heat in the steam generator 1 enters the condenser 5 through the bypass exhaust valve group 6 and the bypass exhaust pipeline 7 for cooling.
Claims (5)
1. The operating system is characterized by comprising a steam generator (1), a main steam main pipe (2), a main steam valve/regulating valve group (3), a steam turbine (4), a condenser (5), a bypass valve group (6), a bypass pipeline (7), a generator (8) and a generator outlet circuit breaker (9);
the outlet of the steam generator (1) is divided into two paths, wherein one path is communicated with the inlet of a steam turbine (4) through a main steam valve/regulating valve group (3), the other path is communicated with the inlet of a condenser (5) through a side exhaust valve group (6), the exhaust port of the steam turbine (4) is communicated with the inlet of the condenser (5), the output shaft of the steam turbine (4) is connected with the driving shaft of a generator (8), and the output end of the generator (8) is connected with a power grid through a generator outlet circuit breaker (9).
2. The shutdown transient non-shutdown operation system according to claim 1, wherein an outlet of the steam generator (1) is communicated with an inlet of the steam turbine (4) through the main steam main pipe (2) and the main steam valve/regulating valve group (3).
3. The shutdown transient non-shutdown operation system according to claim 2, wherein an outlet of the steam generator (1) is communicated with an inlet of the condenser (5) through a bypass valve set (6) and a bypass pipeline (7).
4. A shutdown transient non-stop operation method, based on the shutdown transient non-stop operation system of claim 3, comprising the following steps:
when a reactor is shut down transiently, the steam turbine (4) is not interlocked and shut down, a generator outlet circuit breaker (9) keeps closed, the steam turbine (4) and the generator (8) keep running continuously, steam in the main steam main pipe (2) enters the steam turbine (4) to do work, meanwhile, the steam generator (1) continuously guides out sensible heat and decay heat after the reactor is shut down in a forced circulation mode and generates steam, then the sensible heat and the decay heat are supplied to the steam turbine (4) through the main steam main pipe (2) to do work, the bypass valve group (6) keeps closed, the steam turbine (4) is in a rapid power reduction running state to match the steam generation quantity of the steam generator (1), and the main steam valve/regulating valve group (3) keeps open and gradually regulates the shut down to gradually reduce the power of the steam turbine (4);
when the load of the steam turbine (4) is reduced to a preset load, the steam turbine (4) and the generator (8) are triggered to automatically stop, the generator outlet circuit breaker (9) automatically opens, the main steam valve/regulating valve group (3) automatically closes, the bypass valve group (6) automatically opens, and low-temperature and low-pressure steam generated by reactor waste heat in the steam generator (1) enters the condenser (5) through the bypass valve group (6) and the bypass pipeline (7) for cooling.
5. The shutdown transient non-shutdown operation method according to claim 4, wherein the preset load is 10% of a rated load of the steam turbine (4).
Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202111258578.3A CN113990536B (en) | 2021-10-27 | 2021-10-27 | Shutdown transient non-shutdown operation system and method |
PCT/CN2022/101691 WO2023071254A1 (en) | 2021-10-27 | 2022-06-27 | Reactor shutdown transient non-shutdown operation system and method |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202111258578.3A CN113990536B (en) | 2021-10-27 | 2021-10-27 | Shutdown transient non-shutdown operation system and method |
Publications (2)
Publication Number | Publication Date |
---|---|
CN113990536A true CN113990536A (en) | 2022-01-28 |
CN113990536B CN113990536B (en) | 2024-03-26 |
Family
ID=79742869
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN202111258578.3A Active CN113990536B (en) | 2021-10-27 | 2021-10-27 | Shutdown transient non-shutdown operation system and method |
Country Status (2)
Country | Link |
---|---|
CN (1) | CN113990536B (en) |
WO (1) | WO2023071254A1 (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2023071254A1 (en) * | 2021-10-27 | 2023-05-04 | 西安热工研究院有限公司 | Reactor shutdown transient non-shutdown operation system and method |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN117095841A (en) * | 2023-08-21 | 2023-11-21 | 华能山东石岛湾核电有限公司 | Large interlocking verification method for high-temperature gas cooled reactor and steam turbine and generator |
CN117438119A (en) * | 2023-10-26 | 2024-01-23 | 华能山东石岛湾核电有限公司 | High-temperature gas cooled reactor transition reactor core machine pile interlocking control method and system |
Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5268939A (en) * | 1992-10-19 | 1993-12-07 | General Electric Company | Control system and method for a nuclear reactor |
CN106981322A (en) * | 2017-04-26 | 2017-07-25 | 西安热工研究院有限公司 | A kind of system and method for being used to verify HTGR start and stop heaping equipment function |
CN109147976A (en) * | 2017-06-16 | 2019-01-04 | 苏州热工研究院有限公司 | A kind of stability control equipment applied to nuclear power station cuts machine method |
CN109767852A (en) * | 2019-02-22 | 2019-05-17 | 西安热工研究院有限公司 | A kind of secondary circuit security system and its working method for reactor emergency shut-down |
CN112768101A (en) * | 2021-02-07 | 2021-05-07 | 西安热工研究院有限公司 | System and method for starting nuclear power unit of high-temperature gas cooled reactor by sliding pressure |
CN113187563A (en) * | 2021-05-13 | 2021-07-30 | 西安热工研究院有限公司 | Closed high-temperature gas cooled reactor system and method adopting magnetofluid power generation device |
Family Cites Families (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS56129707A (en) * | 1980-03-14 | 1981-10-12 | Toshiba Corp | Controlling device for cooling of bypass steam in steam turbine |
JP3095485B2 (en) * | 1991-11-13 | 2000-10-03 | 株式会社東芝 | Full capacity turbine bypass nuclear power plant |
CN110259532A (en) * | 2019-07-10 | 2019-09-20 | 西安热工研究院有限公司 | The adaptive steam-supplying system of secondary circuit of PWR nuclear power plant therrmodynamic system and method |
CN111140299B (en) * | 2020-01-14 | 2024-06-04 | 西安热工研究院有限公司 | System and method for configuring heating steam source of deaerator under transient working condition of nuclear power station |
CN113990536B (en) * | 2021-10-27 | 2024-03-26 | 西安热工研究院有限公司 | Shutdown transient non-shutdown operation system and method |
-
2021
- 2021-10-27 CN CN202111258578.3A patent/CN113990536B/en active Active
-
2022
- 2022-06-27 WO PCT/CN2022/101691 patent/WO2023071254A1/en unknown
Patent Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5268939A (en) * | 1992-10-19 | 1993-12-07 | General Electric Company | Control system and method for a nuclear reactor |
CN106981322A (en) * | 2017-04-26 | 2017-07-25 | 西安热工研究院有限公司 | A kind of system and method for being used to verify HTGR start and stop heaping equipment function |
CN109147976A (en) * | 2017-06-16 | 2019-01-04 | 苏州热工研究院有限公司 | A kind of stability control equipment applied to nuclear power station cuts machine method |
CN109767852A (en) * | 2019-02-22 | 2019-05-17 | 西安热工研究院有限公司 | A kind of secondary circuit security system and its working method for reactor emergency shut-down |
CN112768101A (en) * | 2021-02-07 | 2021-05-07 | 西安热工研究院有限公司 | System and method for starting nuclear power unit of high-temperature gas cooled reactor by sliding pressure |
CN113187563A (en) * | 2021-05-13 | 2021-07-30 | 西安热工研究院有限公司 | Closed high-temperature gas cooled reactor system and method adopting magnetofluid power generation device |
Non-Patent Citations (1)
Title |
---|
赵福宇,等: "核反应堆动力学与运行基础", pages: 168 - 169 * |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2023071254A1 (en) * | 2021-10-27 | 2023-05-04 | 西安热工研究院有限公司 | Reactor shutdown transient non-shutdown operation system and method |
Also Published As
Publication number | Publication date |
---|---|
WO2023071254A1 (en) | 2023-05-04 |
CN113990536B (en) | 2024-03-26 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN113990536A (en) | Operation system and method for shutdown transient non-shutdown | |
CN111140299B (en) | System and method for configuring heating steam source of deaerator under transient working condition of nuclear power station | |
CN109296408B (en) | One kind giving mercury vapour turbine vapour source method for handover control | |
CN111255536B (en) | FCB operation method of gas-steam unit power plant | |
CN106368749B (en) | Method for cutting off water side of low-pressure heater to participate in primary frequency modulation loading of unit | |
CN109767852B (en) | Two-loop safety system for reactor emergency shutdown and working method thereof | |
CN108757068B (en) | Combined cycle steam turbine set total cut heat supply control method and device | |
CN207245763U (en) | A kind of high temperature gas cooled reactor Turbine Steam gland sealing steam supply system | |
CN112628711A (en) | Auxiliary engine fault stable combustion control method based on 600MW supercritical unit low load | |
CN111828110B (en) | Control method for automatic steam protection of secondary reheating unit boiler MFT rear auxiliary steam | |
CN110131003A (en) | System and method for starting and stopping secondary loop of high-temperature gas cooled reactor nuclear power unit | |
CN106402840A (en) | Method for cutting out high-pressure heater steam side valve for participating in unit primary frequency modulation and load adding | |
CN106373622A (en) | Active-and-passive-fusion reactor-core waste-heat leading-out system | |
CN113374539B (en) | Steam inlet control system of double-cylinder double-pressure waste heat generating set and steam supplementing control method thereof | |
CN113107625A (en) | Multi-heat-source wide-load low-pressure industrial steam supply system and working method | |
CN112727556B (en) | Peak regulating system with zero output of low-pressure cylinder, heat storage tank and low-pressure heater coupled | |
CN106321173B (en) | Method for cutting off steam side valve of low-pressure heater to participate in primary frequency modulation loading of unit | |
CN114876597B (en) | System and method for realizing island operation of thermal power generating unit by coupling molten salt energy storage | |
CN113178274A (en) | Water vapor working condition switching system and method for nuclear power direct-flow evaporator | |
CN214836588U (en) | Wide-load low-pressure industrial steam supply system with multiple heat sources | |
CN214956034U (en) | Water vapor working condition switching system of nuclear power direct-flow evaporator | |
CN107989662B (en) | Overflow opening control method for steam turbine steam supplementing valve | |
CN210738630U (en) | Exhaust steam treatment system of steam turbine of thermal power plant | |
CN217444077U (en) | Start-stop reactor system of high-temperature gas cooled reactor unit | |
CN213395249U (en) | Built-in reactor starting and stopping device of high-temperature gas cooled reactor secondary loop |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PB01 | Publication | ||
PB01 | Publication | ||
SE01 | Entry into force of request for substantive examination | ||
SE01 | Entry into force of request for substantive examination | ||
GR01 | Patent grant | ||
GR01 | Patent grant |