CN113628771A - Steam generator accident protection system and working method thereof - Google Patents
Steam generator accident protection system and working method thereof Download PDFInfo
- Publication number
- CN113628771A CN113628771A CN202110909407.6A CN202110909407A CN113628771A CN 113628771 A CN113628771 A CN 113628771A CN 202110909407 A CN202110909407 A CN 202110909407A CN 113628771 A CN113628771 A CN 113628771A
- Authority
- CN
- China
- Prior art keywords
- steam generator
- valve
- sodium
- steam
- outlet
- 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.)
- Pending
Links
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
- G21C17/025—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators for monitoring liquid metal coolants
- G21C17/0255—Liquid metal leaks detection
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/06—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium
- F22B1/063—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium for metal cooled nuclear reactors
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/38—Determining or indicating operating conditions in steam boilers, e.g. monitoring direction or rate of water flow through water tubes
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/42—Applications, arrangements, or dispositions of alarm or automatic safety devices
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/006—Details of nuclear power plant primary side of steam generators
-
- 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
Abstract
The invention discloses a steam generator accident protection system and a working method thereof.A pipe side outlet of a steam generator is communicated with a steam output pipeline through a steam quick isolation valve, and an accident drain valve is arranged on a pipeline between a water supply quick isolation valve and the steam generator; the atmosphere relief valve is arranged between the steam generator and the steam quick isolation valve. The outlet of the inlet sodium valve is communicated with a sodium inlet on the shell side of the steam generator, the inlet of the outlet sodium valve is communicated with a sodium outlet on the shell side of the steam generator, and the flow difference meter is communicated with the outlet of the inlet sodium valve and the inlet of the outlet sodium valve; the upper portion of the shell side of the steam generator is provided with a steam generator air cavity, the top of the steam generator air cavity is provided with a hydrogen meter in gas, the lower portion of the shell side of the steam generator is provided with a hydrogen meter in sodium, the system and the working method thereof can monitor small leakage in time, and meanwhile, the coolant of the main loop is prevented from being polluted when large leakage occurs.
Description
Technical Field
The invention belongs to the field of steam generator accident protection, and particularly relates to a steam generator accident protection system and a working method thereof.
Background
In the case of a liquid metal (lithium or sodium) cooled reactor steam generator accident design different from the current mainstream water cooled reactor, the leakage of the heat transfer pipe can cause the chemical reaction between the liquid metal (lithium or sodium) and water (or water vapor), generate hydrogen and release heat, and cause serious pressure transient impact of the system. Therefore, in the overall design of a liquid metal (lithium or sodium) cooled reactor steam generator, it is required that small leaks should be detected in time, high reliability for small leak alarm signals is required, and isolation from the main loop is performed in time. The design requirement under the working condition of large leakage is a reliable large leakage signal, and the pressure of a loop is prevented from rising to an allowable limit; and the fault module is isolated in time to prevent the coolant of the main loop from being polluted. The steam generator accident protection system of a reactor using liquid metal (lithium or sodium) as a coolant should have the functions of monitoring and overpressure protection, isolated discharge and containing sodium water reaction products, however, similar disclosures are not given in the prior art.
Disclosure of Invention
The present invention is directed to overcoming the above-mentioned disadvantages of the prior art and providing a steam generator accident protection system and a method of operating the same that enables timely monitoring of small leaks while preventing contamination of the primary loop coolant in the event of large leaks.
In order to achieve the purpose, the steam generator accident protection system comprises a water supply pipeline, a water supply quick isolation valve, a steam generator, a steam quick isolation valve, a steam output pipeline, an atmospheric release valve, an inlet sodium valve, an outlet sodium valve, a flow difference meter, an accident sodium discharge valve, a primary discharge tank and a rupture membrane;
the water supply pipeline is communicated with a pipe side inlet of the steam generator through a water supply quick isolation valve, a pipe side outlet of the steam generator is communicated with a steam output pipeline through a steam quick isolation valve, and an accident drain valve is arranged on a pipeline between the water supply quick isolation valve and the steam generator; the atmosphere relief valve is arranged between the steam generator and the steam quick isolation valve.
The outlet of the inlet sodium valve is communicated with a sodium inlet on the shell side of the steam generator, the inlet of the outlet sodium valve is communicated with a sodium outlet on the shell side of the steam generator, and the flow difference meter is communicated with the outlet of the inlet sodium valve and the inlet of the outlet sodium valve;
the upper part of the shell side of the steam generator is provided with a steam generator air cavity, the top of the steam generator air cavity is provided with a hydrogen in gas meter, the lower part of the shell side of the steam generator is provided with a hydrogen in sodium meter, and the hydrogen in sodium meter is positioned below the sodium liquid level in the shell side of the steam generator.
The upper side and the lower side of the shell side of the steam generator are both provided with a bubble noise detector.
The bottom outlet of the shell side of the steam generator is communicated with a primary discharge tank through an accident sodium discharge valve.
The outlet of the side surface of the bottom of the steam generator is communicated with the first-stage discharge tank through the rupture membrane.
The argon supply system and the argon supply valve are also included; the argon supply system is communicated with the air cavity of the steam generator through an argon supply valve.
The device also comprises a secondary discharge tank and a sodium vapor cold trap; the top outlet of the first-stage discharge tank is communicated with the upper inlet of the second-stage discharge tank, the bottom outlet of the second-stage discharge tank is communicated with the inlet of the first-stage discharge tank, and the outlet of the second-stage discharge tank is communicated with the sodium vapor cold trap.
And a plurality of temperature sensors are arranged on the pipeline between the rupture disk and the primary discharge tank.
The number of the temperature sensors is four, and the number of the flow rate difference meters is four.
The number of hydrogen in gas and the number of hydrogen in sodium are both two.
The outlet of the accident drain valve is communicated with a drainage flash tank.
A method of operating a steam generator accident protection system, comprising:
1) small leakage condition of steam generator
Judging whether the steam generator has small leakage or not according to the data detected by the two sodium hydrogen meters, the data detected by the two gas hydrogen meters and the data detected by the two bubble noise detectors;
when the steam generator has small leakage, closing the steam quick isolating valve and the water supply quick isolating valve, closing the inlet sodium valve and the outlet sodium valve, opening the atmospheric release valve, performing steam exhaust and water discharge pressure relief on the pipe side of the steam generator, and when the pipe side pressure of the steam generator is reduced to a preset pressure value, automatically closing the atmospheric release valve, opening the accident water discharge valve, and discharging water on the pipe side of the steam generator;
at the same time, discharging sodium in the shell side of the steam generator into a primary discharge tank through an accident sodium discharge valve;
2) large leakage condition of steam generator
Judging whether the steam generator has large leakage or not according to data detected by the four flow difference meters and data detected by the four temperature sensors;
when the steam generator has large leakage, closing the steam quick isolating valve, the water supply quick isolating valve, the inlet sodium valve and the outlet sodium valve, opening the atmospheric release valve, performing steam exhaust, water drainage and pressure relief on the pipe side of the steam generator, automatically closing the atmospheric release valve after the pressure of the pipe side of the steam generator is smaller than a preset pressure value, and automatically opening and closing the emergency drain valve according to the steam-water side pressure of the pipe side of the steam generator to exhaust the residual steam-water of the pipe side of the steam generator;
the mixture of sodium, hydrogen and sodium vapor discharged from the steam generator flows into the primary discharge tank.
In the step 1), when the data detected by any two of the two sodium hydrogen meters and the two gas hydrogen meters exceeds the standard, the steam generator is indicated to have small leakage; and when the data detected by one of the two bubble noise detectors exceeds the standard and the data detected by one of the two sodium hydrogen meters and the two gas hydrogen meters exceeds the standard, indicating that the steam generator has small leakage.
When the flow data detected by two of the four flow difference meters exceed a preset flow deviation alarm value, indicating that the steam generator has large leakage;
when the temperature detected by more than two temperature sensors exceeds the temperature deviation alarm value, the large leakage of the steam generator is indicated.
The invention has the following beneficial effects:
the steam generator accident protection system and the working method thereof adopt the diversity and redundancy combination of the sodium hydrogen meter, the gas hydrogen meter and the bubble noise detector during specific operation, reliably monitor small leakage of the steam generator, and simultaneously control faults when the steam generator leaks. In addition, the invention adopts a dual-action mechanism of the steam generator air cavity and the rupture disk, effectively relieves the pressure transient state during large leakage and is beneficial to ensuring the operation safety of the steam generator and the communicated equipment.
Drawings
FIG. 1 is a schematic structural diagram of the present invention.
Wherein, 1 is an inlet sodium valve, 2 is a steam generator, 3 is a steam generator air cavity, 4 is an outlet sodium valve, 4-1 is a flow difference meter, 5 is a steam quick isolating valve, 6 is an atmospheric release valve, 7 is a water supply quick isolating valve, 8 is an accident drain valve, 9 is a hydrophobic flash tank, 10 is a rupture membrane, 10-1 is a temperature sensor, 11 is an accident sodium discharge valve, 12 is a primary discharge tank, 13 is a secondary discharge tank, 14 is a sodium steam cold trap, 15-1 is a sodium hydrogen meter, 15-2 is a gas hydrogen meter, 16 is a bubble noise detector, 17 is an argon gas supply system, and 18 is an argon gas supply valve.
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 steam generator accident protection system of the present invention includes a water supply pipeline, a water supply quick isolation valve 7, a steam generator 2, a steam quick isolation valve 5, a steam output pipeline, an atmospheric release valve 6, an inlet sodium valve 1, an outlet sodium valve 4, a flow rate difference meter 4-1, an accident sodium discharge valve 11, a primary discharge tank 12 and a rupture membrane 10;
the water supply pipeline is communicated with a pipe side inlet of the steam generator 2 through a water supply quick isolation valve 7, a pipe side outlet of the steam generator 2 is communicated with a steam output pipeline through a steam quick isolation valve 5, an accident drain valve 8 is arranged on the pipeline between the water supply quick isolation valve 7 and the steam generator 2, and an outlet of the accident drain valve 8 is communicated with a drainage flash tank 9; an atmospheric relief valve 6 is provided between the steam generator 2 and the steam quick isolation valve 5.
The outlet of the inlet sodium valve 1 is communicated with the sodium inlet on the shell side of the steam generator 2, the inlet of the outlet sodium valve 4 is communicated with the sodium outlet on the shell side of the steam generator 2, the four flow difference meters 4-1 are communicated with the outlet of the inlet sodium valve 1 and the inlet of the outlet sodium valve 4, and the flow deviation action fixed value is 20%.
The upper part of the shell side of the steam generator 2 is provided with a steam generator air cavity 3, an argon gas supply system 17 is communicated with the steam generator air cavity 3 through an argon gas supply valve 18, the top of the steam generator air cavity 3 is provided with two hydrogen meters in gas 15-2, the lower part of the shell side of the steam generator 2 is provided with two hydrogen meters in sodium 15-1, wherein each hydrogen meter in sodium 15-1 is positioned below the sodium liquid level in the shell side of the steam generator 2.
The bubble noise detector 16 is installed at both the upper and lower sides of the shell side of the steam generator 2.
The bottom outlet of the shell side of the steam generator 2 is communicated with a primary discharge tank 12 through an accident sodium discharge valve 11, the top outlet of the primary discharge tank 12 is communicated with the upper inlet of a secondary discharge tank 13, the bottom outlet of the secondary discharge tank 13 is communicated with the inlet of the primary discharge tank 12, and the outlet of the secondary discharge tank 13 is communicated with a sodium steam cold trap 14.
An outlet on the side surface of the bottom of the steam generator 2 is communicated with a first-stage discharge tank 12 through a rupture membrane 10, and a plurality of temperature sensors 10-1 are arranged on a pipeline between the rupture membrane 10 and the first-stage discharge tank 12, wherein the fixed value of the temperature deviation action is 100 ℃.
The working method of the steam generator accident protection system comprises the following steps:
1) small leakage condition of steam generator 2
Judging whether the steam generator 2 has small leakage or not according to the data detected by the two sodium hydrogen meters 15-1, the data detected by the two gas hydrogen meters 15-2 and the data detected by the two bubble noise detectors 16, wherein when the data detected by any one of the two sodium hydrogen meters 15-1 and the two gas hydrogen meters 15-2 exceeds the standard, the steam generator 2 has small leakage; when the data detected by one of the two bubble noise detectors 16 exceeds the standard and the data detected by one of the two sodium hydrogen meters 15-1 and the two gas hydrogen meters 15-2 exceeds the standard, it is indicated that the steam generator 2 has small leakage;
when the steam generator 2 has small leakage, closing the steam quick isolation valve 5 and the water supply quick isolation valve 7, closing the inlet sodium valve 1 and the outlet sodium valve 4, opening the atmospheric release valve 6, performing quick steam exhaust, water drainage and pressure relief on the tube side of the steam generator 2, and when the pressure of the tube side of the steam generator 2 is reduced to a preset pressure value, automatically closing the atmospheric release valve 6, opening the accident drain valve 8, and discharging water on the tube side of the steam generator 2 into the drain flash tank 9;
at the same time, the argon supply valve 18 is opened, and sodium in the shell side of the steam generator 2 is discharged into the primary discharge tank 12 through the accident sodium discharge valve 11 under the pressure of argon gas, which is higher than the vapor-water side pressure, so as to accelerate the sodium discharge speed while reducing the amount of water leaked in.
2) Large leakage condition of steam generator 2
When the steam generator 2 has large leakage, severe sodium water reaction occurs in the steam generator 2 to form severe pressure transient state, and the sodium flow at the inlet and the outlet of the steam generator 2 has huge deviation, namely when the flow data detected by two of the four flow difference meters 4-1 exceed the preset flow deviation alarm value, the steam generator 2 has large leakage;
at the moment, the steam generator air cavity 3 can compensate the impact of a part of pressure transients, when the internal pressure of the shell side of the steam generator 2 is higher than the action value of the rupture membrane 10, sodium in the shell side of the steam generator 2 is discharged into the primary discharge tank 12 through the rupture membrane 10, the temperature detected by the 4 temperature sensors 10-1 is increased, and when the temperature detected by the two temperature sensors 10-1 exceeds the temperature deviation alarm value, the steam generator 2 is indicated to have large leakage;
closing the steam quick isolating valve 5, the water supply quick isolating valve 7, the inlet sodium valve 1 and the outlet sodium valve 4, opening the atmospheric release valve 6, performing quick steam exhaust, water drainage and pressure relief on the pipe side of the steam generator 2, automatically closing the atmospheric release valve 6 after the pressure of the pipe side of the steam generator 2 is smaller than a preset pressure value, and automatically opening and closing a follow-up accident drain valve 8 according to the steam-water side pressure of the pipe side of the steam generator 2 so as to exhaust the residual steam-water of the pipe side of the steam generator 2;
the mixture of sodium, hydrogen and sodium vapor discharged by the steam generator 2 flows into a primary discharge tank 12, wherein the mixed gas formed by the hydrogen and the sodium vapor enters a secondary discharge tank 13 through the top of the primary discharge tank 12, most of the sodium vapor is condensed and separated in the secondary discharge tank 13 and is discharged into the primary discharge tank 12 through the bottom of the secondary discharge tank 13 in a backflow manner, the rest sodium vapor is condensed and collected in a sodium vapor cold trap 14, and the hydrogen generated by the sodium water reaction is discharged to the atmosphere;
after the large leakage happens, the accident sodium discharge valve 11 can be opened simultaneously for discharging sodium rapidly, sodium in the shell side of the steam generator 2 is discharged into the first-stage discharge tank 12, the argon gas supply valve 18 is opened in the sodium discharge process, and power is provided by argon gas output by the argon gas supply system 17, so that sodium in the shell side of the steam generator 2 is discharged rapidly, and meanwhile, the amount of water leaked is reduced.
Claims (10)
1. A steam generator accident protection system is characterized by comprising a water supply pipeline, a water supply quick isolation valve (7), a steam generator (2), a steam quick isolation valve (5), a steam output pipeline, an atmospheric release valve (6), an inlet sodium valve (1), an outlet sodium valve (4), a flow difference meter (4-1), an accident sodium discharge valve (11), a primary discharge tank (12) and a rupture membrane (10);
a water supply pipeline is communicated with a pipe side inlet of the steam generator (2) through a water supply quick isolation valve (7), a pipe side outlet of the steam generator (2) is communicated with a steam output pipeline through a steam quick isolation valve (5), and an accident drain valve (8) is arranged on a pipeline between the water supply quick isolation valve (7) and the steam generator (2); the atmospheric release valve (6) is arranged between the steam generator (2) and the steam quick isolation valve (5);
an outlet of the inlet sodium valve (1) is communicated with a sodium inlet on the shell side of the steam generator (2), an inlet of the outlet sodium valve (4) is communicated with a sodium outlet on the shell side of the steam generator (2), and the outlet of the inlet sodium valve (1) and an inlet of the outlet sodium valve (4) are communicated with the flow rate difference meter (4-1);
a steam generator air cavity (3) is arranged at the upper part of the shell side of the steam generator (2), an in-gas hydrogen meter (15-2) is arranged at the top of the steam generator air cavity (3), a sodium in-hydrogen meter (15-1) is arranged at the lower part of the shell side of the steam generator (2), wherein the sodium in-hydrogen meter (15-1) is positioned below the sodium liquid level in the shell side of the steam generator (2);
the upper side and the lower side of the shell side of the steam generator (2) are provided with bubble noise detectors (16);
the bottom outlet of the shell side of the steam generator (2) is communicated with a primary discharge tank (12) through an accident sodium discharge valve (11);
an outlet on the side surface of the bottom of the steam generator (2) is communicated with a primary discharge tank (12) through a rupture disk (10).
2. The steam generator accident protection system of claim 1, further comprising an argon gas supply system (17) and an argon gas supply valve (18); the argon supply system (17) is communicated with the steam generator air cavity (3) through an argon supply valve (18).
3. Steam generator accident protection system according to claim 1, further comprising a secondary drain tank (13) and a sodium vapour cold trap (14); the top outlet of the first-stage discharge tank (12) is communicated with the upper inlet of the second-stage discharge tank (13), the bottom outlet of the second-stage discharge tank (13) is communicated with the inlet of the first-stage discharge tank (12), and the outlet of the second-stage discharge tank (13) is communicated with the sodium vapor cold trap (14).
4. Steam generator accident protection system according to claim 1, characterized in that several temperature sensors (10-1) are installed on the piping between the rupture disk (10) and the primary discharge tank (12).
5. Steam generator accident protection system according to claim 4, characterized in that the number of temperature sensors (10-1) is four and the number of flow rate difference meters (4-1) is four.
6. Steam generator accident protection system according to claim 5, characterized in that the number of hydrogen in gas meters (15-2) and the number of hydrogen in sodium meters (15-1) are both two.
7. Steam generator accident protection system according to claim 1, characterized in that the outlet of the accident drain valve (8) is connected to a hydrophobic flash tank (9).
8. A method of operating the steam generator accident protection system of claim 5, comprising:
1) small leakage condition of steam generator (2)
Judging whether the steam generator (2) has small leakage or not according to the data detected by the two sodium hydrogen meters (15-1), the data detected by the two gas hydrogen meters (15-2) and the data detected by the two bubble noise detectors (16);
when the steam generator (2) has small leakage, closing the steam quick isolating valve (5) and the water supply quick isolating valve (7), closing the inlet sodium valve (1) and the outlet sodium valve (4), opening the atmospheric release valve (6), performing steam exhaust, water drainage and pressure relief on the pipe side of the steam generator (2), and when the pressure of the pipe side of the steam generator (2) is reduced to a preset pressure value, automatically closing the atmospheric release valve (6), opening the accident drain valve (8), and discharging water on the pipe side of the steam generator (2);
at the same time, the sodium in the shell side of the steam generator (2) is discharged into a primary discharge tank (12) through an accident sodium discharge valve (11);
2) large leakage working condition of steam generator (2)
Judging whether the steam generator (2) has large leakage or not according to data detected by the four flow difference meters (4-1) and data detected by the four temperature sensors (10-1);
when the steam generator (2) has large leakage, closing the steam quick isolating valve (5), the water supply quick isolating valve (7), the inlet sodium valve (1) and the outlet sodium valve (4), opening the atmospheric release valve (6), performing steam exhaust, water drainage and pressure relief on the pipe side of the steam generator (2), automatically closing the atmospheric release valve (6) after the pressure of the pipe side of the steam generator (2) is smaller than a preset pressure value, and automatically opening and closing the accident drain valve (8) according to the steam-water side pressure of the pipe side of the steam generator (2) to drain residual steam water on the pipe side of the steam generator (2);
the mixture of sodium, hydrogen and sodium vapor discharged from the steam generator (2) flows into a primary discharge tank (12).
9. The operating method of the steam generator accident protection system according to claim 8, wherein in step 1), when the detected data of any two of the two sodium hydrogen meters (15-1) and the two gas hydrogen meters (15-2) exceed the standard, it is indicated that the steam generator (2) has a small leakage; when the data detected by one of the two bubble noise detectors (16) exceeds the standard and the data detected by one of the two sodium hydrogen meters (15-1) and the two gas hydrogen meters (15-2) exceeds the standard, the small leakage of the steam generator (2) is indicated.
10. The method for operating a steam generator accident protection system according to claim 8, wherein a large leakage of the steam generator (2) is indicated when two of the four flow rate difference meters (4-1) detect flow data exceeding a preset flow rate deviation alarm value;
when the temperature detected by more than two temperature sensors (10-1) exceeds the temperature deviation alarm value, the large leakage of the steam generator (2) is indicated.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110909407.6A CN113628771A (en) | 2021-08-09 | 2021-08-09 | Steam generator accident protection system and working method thereof |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110909407.6A CN113628771A (en) | 2021-08-09 | 2021-08-09 | Steam generator accident protection system and working method thereof |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN113628771A true CN113628771A (en) | 2021-11-09 |
Family
ID=78383711
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202110909407.6A Pending CN113628771A (en) | 2021-08-09 | 2021-08-09 | Steam generator accident protection system and working method thereof |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN113628771A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114264416A (en) * | 2021-12-24 | 2022-04-01 | 西安交通大学 | Test system and method for researching internal leakage of steam generator |
| CN114459013A (en) * | 2022-01-27 | 2022-05-10 | 华能山东石岛湾核电有限公司 | Protection system and method for high-temperature gas cooled reactor steam generator |
-
2021
- 2021-08-09 CN CN202110909407.6A patent/CN113628771A/en active Pending
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114264416A (en) * | 2021-12-24 | 2022-04-01 | 西安交通大学 | Test system and method for researching internal leakage of steam generator |
| CN114264416B (en) * | 2021-12-24 | 2022-08-26 | 西安交通大学 | Test system and method for researching internal leakage of steam generator |
| CN114459013A (en) * | 2022-01-27 | 2022-05-10 | 华能山东石岛湾核电有限公司 | Protection system and method for high-temperature gas cooled reactor steam generator |
| CN114459013B (en) * | 2022-01-27 | 2023-09-08 | 华能山东石岛湾核电有限公司 | Protection system and method for high-temperature gas cooled reactor steam generator |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN113628771A (en) | Steam generator accident protection system and working method thereof | |
| US5309487A (en) | Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems | |
| US11646123B2 (en) | Three-way valve operational to both transfer steam to a decontamination water tank under one accident situation and discharge the steam to atmosphere under a different accident situation | |
| CN107068214B (en) | Nuclear power plant steam atmosphere discharge device and two-loop pressure release method | |
| US20200194135A1 (en) | Depressurisation valve | |
| US5596613A (en) | Pressure suppression containment system for boiling water reactor | |
| JPH0319519B2 (en) | ||
| IE57242B1 (en) | Nuclear reactor power plant | |
| CN215730888U (en) | Steam generator accident protection system | |
| CN206946957U (en) | For the pipe-line system for preventing presurized water reactor radioactive substance from discharging | |
| US5802128A (en) | Device for recovery of fluid contained in the coolant circuit of a nuclear reactor | |
| CN110388239B (en) | Nuclear power station moisture separator reheater system | |
| CN111681794A (en) | Full-range SGTR accident handling method and system for pressurized water reactor nuclear power plant | |
| CN110911024A (en) | Sustained release device for steam generator heat transfer tube rupture accident | |
| KR100363574B1 (en) | Method for controling of passive secondary condensing system in nuclear power plant | |
| US3748227A (en) | Containment system for a sodium cooled reactor | |
| US3488254A (en) | Containment arrangement for water cooled nuclear reactor installation | |
| JP7417508B2 (en) | Reactor containment vessel venting method | |
| JPS63289488A (en) | Pressure controller for containment vessel of nuclear reactor | |
| CN217519831U (en) | Nuclear steam supply system capable of preventing radioactive substances from escaping | |
| CN104112481A (en) | Releasing device capable of reducing accident source terms | |
| CN104879737B (en) | Steam generator secondary side partition method in kilowatt pressurized water reactor nuclear power station | |
| RU2002321C1 (en) | Passive residual-heat transfer system for nuclear reactor | |
| CN114999681B (en) | High-temperature gas cooled reactor, high-temperature gas cooled reactor waste heat discharging system and operation method thereof | |
| JPH0545489A (en) | Pressure reducing equipment for pressure vessel of reactor |
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 |