CN113982700B - High-temperature gas cooled reactor shaft seal steam supply system - Google Patents
High-temperature gas cooled reactor shaft seal steam supply system Download PDFInfo
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- CN113982700B CN113982700B CN202111301561.1A CN202111301561A CN113982700B CN 113982700 B CN113982700 B CN 113982700B CN 202111301561 A CN202111301561 A CN 202111301561A CN 113982700 B CN113982700 B CN 113982700B
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- steam
- isolation valve
- pipeline
- shaft seal
- communicated
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- 230000005540 biological transmission Effects 0.000 claims abstract description 49
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 16
- 238000002955 isolation Methods 0.000 claims description 103
- 230000001105 regulatory effect Effects 0.000 claims description 16
- 239000007789 gas Substances 0.000 abstract description 18
- 239000002918 waste heat Substances 0.000 abstract description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000001307 helium Substances 0.000 description 2
- 229910052734 helium Inorganic materials 0.000 description 2
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000007789 sealing Methods 0.000 description 2
- 238000004891 communication Methods 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000003584 silencer Effects 0.000 description 1
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D11/00—Preventing or minimising internal leakage of working-fluid, e.g. between stages
- F01D11/02—Preventing or minimising internal leakage of working-fluid, e.g. between stages by non-contact sealings, e.g. of labyrinth type
- F01D11/04—Preventing or minimising internal leakage of working-fluid, e.g. between stages by non-contact sealings, e.g. of labyrinth type using sealing fluid, e.g. steam
Abstract
The invention provides a high-temperature gas cooled reactor shaft seal steam supply system, which belongs to the technical field of nuclear power and comprises: a steam generator; a steam turbine system; a shaft seal structure; a third steam transmission pipeline; an auxiliary electric boiler; according to the high-temperature gas cooled reactor shaft seal steam supply system, after the emergency shutdown, the third steam transmission pipeline is arranged, high-temperature steam is generated by utilizing water stored in the steam generator and waste heat of a loop through the third steam transmission pipeline, so that steam is provided for a shaft seal structure, the shaft seal of a steam turbine is prevented from being supplied by steam, and the safety and reliability of the steam turbine in the high-temperature gas cooled reactor after the emergency shutdown are greatly improved.
Description
Technical Field
The invention relates to the technical field of nuclear power, in particular to a high-temperature gas cooled reactor shaft seal steam supply system.
Background
The main function of the turbine shaft seal system of the high-temperature gas cooled reactor is to provide steam with certain temperature and pressure for the turbine before, during and during the shutdown of the turbine, prevent the steam of the high-pressure cylinder part of the turbine from leaking outwards, and ensure the operation safety of the turbine and the thermal efficiency of the turbine.
When the unit normally operates, the auxiliary electric boiler is in a hot standby state, the steam turbine shaft seal system seals the low-pressure cylinder shaft seal by utilizing the leakage steam of the high-pressure cylinder shaft seal, and the steam turbine realizes self-sealing; in a cold starting working condition, the steam turbine shaft seal system supplies steam by the auxiliary steam system; when the steam turbine is started in an extremely hot state or is stopped in a planned mode, the steam is supplied by the main steam system through the steam turbine shaft seal system.
In the event of a reactor emergency shutdown, the primary steam system can no longer provide a source of steam. At this time, the auxiliary electric boiler can not provide required steam for the turbine shaft seal system immediately, and the shaft seal of turbine has the risk of outage with the steam, if the condition of outage appears in the shaft seal of turbine with the steam, can cause shaft seal structure cooling heat altered shape to can lead to shaft seal and rotor friction and produce vibration, and then probably make the rotor take place to damage.
Disclosure of Invention
Therefore, the invention aims to overcome the defect that in the prior art, when a reactor is in emergency shutdown, the shaft seal steam of the steam turbine is in outage, so that a rotor is possibly damaged, and further provides a high-temperature gas cooled reactor shaft seal steam supply system.
In order to solve the technical problems, the invention provides a high-temperature gas cooled reactor shaft seal steam supply system, which comprises:
the inlet of the steam generator is connected with the main water supply device through a water supply pipeline; the outlet of the steam generator is communicated with the atmosphere through a steam exhaust pipeline; the exhaust pipeline is provided with a third isolation valve and a fourth isolation valve;
the steam turbine system is communicated with the outlet of the steam generator through a first steam transmission pipeline; a first isolation valve and a fourteenth isolation valve are arranged on the first steam transmission pipeline;
the shaft seal structure is communicated with an outlet of the steam generator through a second steam transmission pipeline; a second isolation valve is arranged on the second steam transmission pipeline;
the first end of the third steam transmission pipeline is communicated with the third isolation valve and the fourth isolation valve of the steam exhaust pipeline through a tee joint, and the second end of the third steam transmission pipeline is communicated with the front end of the second isolation valve of the second steam transmission pipeline through a tee joint; a fifth isolation valve and a thirteenth isolation valve are arranged on the third steam transmission pipeline;
the auxiliary electric boiler is communicated with the shaft seal structure through a steam supply pipeline; and a sixth isolation valve is arranged on the steam supply pipeline.
As a preferable scheme, an outlet converging pipeline is communicated with the outlet of the steam generator; a seventh isolation valve is arranged on the outlet converging pipeline; one end of the outlet converging pipeline far away from the steam generator is communicated with the steam exhaust pipeline and the starting end of the first steam transmission pipeline through a tee joint.
As a preferable scheme, the rear end of the second isolation valve of the second steam transmission pipeline is sequentially provided with a first regulating valve and an eighth isolation valve.
Preferably, a first attemperator is arranged at the rear end of the eighth isolation valve of the second steam transmission pipeline.
As a preferable scheme, two ends of the second isolation valve and the eighth isolation valve of the second steam transmission pipeline are respectively communicated with two ends of the first bypass pipeline.
Preferably, a ninth isolation valve is arranged on the first bypass pipeline.
As a preferable scheme, the steam supply pipeline and the second steam transmission pipeline are communicated with the shaft seal pipeline through a tee joint; the shaft seal pipeline is provided with a first branch and a second branch which are communicated; the first branch is communicated with the high pressure side of the high pressure cylinder of the shaft seal structure; the second branch is communicated with other positions of the shaft seal structure through branch pipes.
Preferably, a second desuperheater is arranged on the second branch.
Preferably, a second regulating valve and a tenth isolating valve are sequentially arranged at the rear end of the sixth isolating valve of the steam supply pipeline.
As a preferable scheme, two ends of a sixth isolation valve and a tenth isolation valve of the second steam transmission pipeline are respectively communicated with two ends of a second bypass pipeline; an eleventh isolation valve is arranged on the second bypass pipeline.
The technical scheme of the invention has the following advantages:
1. the invention provides a high-temperature gas cooled reactor shaft seal steam supply system, which comprises: the system comprises a steam generator, a steam turbine system, a shaft seal structure, a third steam transmission pipeline and an auxiliary electric boiler; through the setting of third steam delivery pipeline, can be after the emergency shutdown, utilize the waste heat of water storage and a return circuit in the steam generator through the third steam delivery pipeline, produce high temperature steam, provide steam for the bearing seal structure, avoid the bearing seal steam of steam turbine to cut off and supply, greatly improved the security and the reliability of steam turbine after the emergency shutdown in the high temperature gas cooled reactor.
2. According to the high-temperature gas cooled reactor shaft seal steam supply system, the steam supply flow rate of the shaft seal structure is adjusted through setting of the first regulating valve.
3. According to the high-temperature gas cooled reactor shaft seal steam supply system provided by the invention, the steam temperature of the high-pressure side of the high-pressure cylinder of the shaft seal structure is regulated through the first attemperator, and the steam temperatures of the low-pressure side of the high-pressure cylinder and the two sides of the low-pressure cylinder of the shaft seal structure are regulated through the second attemperator, so that the matching of the temperature of shaft seal steam and the rotor of a steam turbine is ensured, and the safety of a unit is ensured.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings that are needed in the description of the embodiments or the prior art will be briefly described, and it is obvious that the drawings in the description below are some embodiments of the present invention, and other drawings can be obtained according to the drawings without inventive effort for a person skilled in the art.
FIG. 1 is a schematic diagram of a first construction of a shaft seal steam supply system for a high temperature gas cooled reactor according to the present invention.
FIG. 2 is a second schematic diagram of the shaft seal steam supply system of the high temperature gas cooled reactor of the present invention.
Reference numerals illustrate:
1. a steam generator; 2. a main water supply device; 3. a steam turbine system; 4. an auxiliary electric boiler; 5. a muffler; 6. a high pressure side shaft seal of the high pressure cylinder; 7. a high pressure cylinder low pressure side shaft seal; 8. a valve end shaft seal is regulated by a low pressure cylinder; 9. a motor end shaft seal of the low pressure cylinder; 10. a shaft seal structure; 11. a first isolation valve; 12. a second isolation valve; 13. a third isolation valve; 14. a fourth isolation valve; 15. a fifth isolation valve; 16. a sixth isolation valve; 17. a seventh isolation valve; 18. an eighth isolation valve; 19. a ninth isolation valve; 20. a tenth isolation valve; 21. an eleventh isolation valve; 22. a twelfth isolation valve; 23. a thirteenth isolation valve; 24. a first desuperheater; 25. a second desuperheater; 26. a self-condensing water device; 27. a first regulating valve; 28. a second regulating valve; 29. a water supply line; 30. an outlet merging pipeline; 31. a steam exhaust pipeline; 32. a first steam delivery pipeline; 33. a second steam delivery pipeline; 34. a third steam transmission pipeline; 35. a shaft seal pipeline; 36. a steam supply pipeline; 37. a first branch; 38. a second branch; 39. a first branch circuit; 40. a second branch circuit; 41. a third branch circuit; 42. a first bypass line; 43. a second bypass line; 44. fourteenth isolation valve.
Detailed Description
The following description of the embodiments of the present invention will be made apparent and fully in view of the accompanying drawings, in which some, but not all embodiments of the invention are shown. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
In the description of the present invention, it should be noted that the directions or positional relationships indicated by the terms "center", "upper", "lower", "left", "right", "vertical", "horizontal", "inner", "outer", etc. are based on the directions or positional relationships shown in the drawings, are merely for convenience of describing the present invention and simplifying the description, and do not indicate or imply that the devices or elements referred to must have a specific orientation, be configured and operated in a specific orientation, and thus should not be construed as limiting the present invention.
In the description of the present invention, it should be noted that, unless explicitly specified and limited otherwise, the terms "mounted," "connected," and "connected" are to be construed broadly, and may be either fixedly connected, detachably connected, or integrally connected, for example; can be mechanically or electrically connected; can be directly connected or indirectly connected through an intermediate medium, and can be communication between two elements. The specific meaning of the above terms in the present invention will be understood in specific cases by those of ordinary skill in the art.
In addition, the technical features of the different embodiments of the present invention described below may be combined with each other as long as they do not collide with each other.
The high-temperature gas cooled reactor shaft seal steam supply system provided by the embodiment, as shown in figures 1 and 2, comprises a steam generator 1; the inlet end of the steam generator 1 is connected with the main water supply device 2 through a water supply pipeline 29; the outlet end of the steam generator 1 is communicated with the initial end of an outlet converging pipeline 30, and the tail end of the outlet converging pipeline 30 is respectively communicated with the initial ends of a steam exhaust pipeline 31 and a first steam transmission pipeline 32 through a tee joint; the first steam transmission pipeline 32 is communicated with the initial end of the second steam transmission pipeline 33 through a tee joint, and the tail end of the second steam transmission pipeline 33 is communicated with the shaft seal pipeline 35.
A seventh isolation valve 17 is arranged on the outlet merging pipeline 30; the tail end of the first steam transmission pipeline 32 is communicated with the steam turbine system 3, and the first steam transmission pipeline 32 is provided with a first isolation valve 11 and a fourteenth isolation valve 44; the tail end of the exhaust pipeline 31 is communicated with the atmosphere, and the exhaust pipeline 31 is provided with a third isolation valve 13, a fourth isolation valve 14 and a silencer 5; the second steam transmission pipeline 33 is provided with a second isolation valve 12, the rear end of the first isolation valve of the first steam transmission pipeline 32 is communicated with the starting end of the second steam transmission pipeline 33 through a tee joint, and the tail end of the second steam transmission pipeline 33 is communicated with the shaft seal pipeline 35.
A second isolation valve 12, a first regulating valve 27 and an eighth isolation valve 18 are sequentially arranged on the second steam conveying pipe; a first bypass pipeline 42 is connected to two ends of the second isolation valve 12 and the eighth isolation valve 18 of the second steam delivery pipe, and a ninth isolation valve 19 is arranged on the first bypass pipeline 42; a first desuperheater 24 is also arranged on the second steam delivery line 33, the first desuperheater 24 being connected to a self-condensing water device 26.
The auxiliary electric boiler 4 is communicated with the shaft seal structure 10 through a steam supply pipeline 36; a sixth isolation valve 16, a second regulating valve 28 and a tenth isolation valve 20 are arranged on the steam supply pipeline 36 in sequence; a second bypass line 43 is connected to both ends of the sixth isolation valve 16 and the tenth isolation valve 20 of the steam supply line 36, and an eleventh isolation valve 21 is provided in the second bypass line 43.
Further, the second steam delivery pipeline 33 and the steam supply pipeline 36 are communicated with the initial end of the shaft seal pipeline 35 through a tee joint, and the tail end of the shaft seal pipeline 35 is communicated with the shaft seal structure 10;
further, the shaft seal pipeline 35 is communicated with the first branch 37 and the second branch 38 through a tee joint; the first branch 37 is communicated with the high-pressure cylinder high-pressure side bearing seal 6 of the shaft seal structure 10; the second branch 38 is communicated with the high-pressure cylinder low-pressure side shaft seal 7 through a first branch 39, is communicated with the low-pressure cylinder valve regulating end 8 shaft seal through a second branch 40, is communicated with the low-pressure cylinder motor end shaft seal 9 through a third branch 41, and is provided with a second desuperheater 25 on the second branch 38, and the second desuperheater 25 is connected with the self-condensation water device 26.
A third steam transmission pipeline 34 is arranged on the steam exhaust pipeline 31 and the second steam transmission pipeline 33 in a communicating way, specifically, the starting end of the third steam transmission pipeline 34 is communicated with the position between the third isolation valve 13 and the fourth isolation valve 14 of the steam exhaust pipeline 31 through a tee joint, and the tail end of the third steam transmission pipeline 34 is communicated with the front end of the second isolation valve 12 of the second steam transmission pipeline 33 through a tee joint. A fifth isolation valve 15 and a thirteenth isolation valve 23 are arranged on the third steam line 34.
Application method and principle
The high-temperature gas cooled reactor demonstration project steam generator 1 adopts a vertical and direct-current spiral heat exchange tube structure, the outer side of the heat exchange tube is a primary side, helium is adopted as a medium, and in normal operation, the high-temperature gas cooled reactor demonstration project steam generator is driven by a main helium fan to flow downwards from top to bottom, and the temperature is transited from 750 ℃ to 243 ℃; the heat exchange tube is internally provided with a secondary side, desalted water from the main water supply device 2 enters the steam generator 1 through the twelfth isolation valve 22, the high-pressure water supply at 205 ℃ is converted into main steam at 566 ℃, and the main steam enters the steam turbine system 3 through the seventh isolation valve 17, the first isolation valve 11 and the fourteenth isolation valve 44 and enters the shaft seal structure 10 through the second isolation valve 12 and the eighth isolation valve 18.
In normal operation, the auxiliary electric boiler 4 is in a hot standby state, the shaft seal structure 10 seals the shaft seal of the low-pressure cylinder by utilizing the leakage steam of the shaft seal of the high-pressure cylinder, and the steam turbine system 3 realizes self-sealing; in cold start conditions, the shaft seal structure 10 is supplied with steam from the auxiliary electric boiler 4.
After the shutdown, if the steam in the steam generator 1 needs to be exhausted, the seventh isolation valve 17, the third isolation valve 13 and the fourth isolation valve 14 are opened, the twelfth isolation valve 22, the second isolation valve 12, the fifth isolation valve 15 and the fourteenth isolation valve 44 are closed, and the steam is exhausted to the atmosphere through the muffler 5 through the exhaust pipe 31.
At the time of emergency shutdown of an accident, the seventh isolation valve 17 and the third isolation valve 13 are opened, and the twelfth isolation valve 22, the first isolation valve 11, the fourth isolation valve 14 and the fourteenth isolation valve 44 are closed; simultaneously, the fifth isolation valve 15, the thirteenth isolation valve 23, the second isolation valve 12 and the eighth isolation valve 18 are opened, so that the stored steam in the steam generator 1 is led to the shaft seal structure 10 to supply steam for the shaft seal structure, and the flow rate of the steam used by the shaft seal structure 10 is regulated by regulating the opening of the first regulating valve 27; adjusting the steam temperature of the high pressure side bearing seal 6 of the high pressure cylinder in the shaft seal structure 10 by the first attemperator 24; the steam temperatures of the high-pressure cylinder low-pressure side shaft seal 7, the low-pressure cylinder valve adjusting end shaft seal 8 and the low-pressure motor end shaft seal 9 in the shaft seal structure 10 are adjusted through the second attemperator 25, so that the temperature of steam in the shaft seal structure 10 is matched with that of a rotor in the steam turbine system 3, and the safety of a unit is guaranteed.
According to the scheme, the third steam transmission pipeline is additionally arranged on the steam exhaust pipeline, high-temperature steam is provided for the shaft seal structure through the third steam transmission pipeline when the emergency shutdown is performed, the problem that the shaft seal steam of the steam turbine is supplied discontinuously after the emergency shutdown is solved, and the safety and reliability of the steam turbine in the high-temperature gas cooled reactor after the emergency shutdown are greatly improved.
It is apparent that the above examples are given by way of illustration only and are not limiting of the embodiments. Other variations or modifications of the above teachings will be apparent to those of ordinary skill in the art. It is not necessary here nor is it exhaustive of all embodiments. While still being apparent from variations or modifications that may be made by those skilled in the art are within the scope of the invention.
Claims (6)
1. A high temperature gas cooled reactor shaft seal steam supply system comprising:
the inlet of the steam generator (1) is connected with the main water supply device (2) through a water supply pipeline (29); the outlet of the steam generator (1) is communicated with the atmosphere through a steam exhaust pipeline (31); the steam exhaust pipeline (31) is provided with a third isolation valve (13) and a fourth isolation valve (14);
the steam turbine system (3) is communicated with the outlet of the steam generator (1) through a first steam transmission pipeline (32); a first isolation valve (11) and a fourteenth isolation valve (44) are arranged on the first steam transmission pipeline (32);
the shaft seal structure (10) is communicated with the outlet of the steam generator (1) through a second steam transmission pipeline (33); a second isolation valve (12) is arranged on the second steam transmission pipeline (33);
the first end of the third steam transmission pipeline (34) is communicated with the position between the third isolation valve (13) and the fourth isolation valve (14) of the steam exhaust pipeline (31) through a tee joint, and the second end of the third steam transmission pipeline is communicated with the front end of the second isolation valve (12) of the second steam transmission pipeline (33) through a tee joint; a fifth isolation valve (15) and a thirteenth isolation valve (23) are arranged on the third steam transmission pipeline (34);
the auxiliary electric boiler (4) is communicated with the shaft seal structure (10) through a steam supply pipeline (36); a sixth isolation valve (16) is arranged on the steam supply pipeline (36);
the rear end of the sixth isolation valve (16) of the steam supply pipeline (36) is sequentially provided with a second regulating valve (28) and a tenth isolation valve (20);
the rear end of the second isolation valve (12) of the second steam transmission pipeline (33) is sequentially provided with a first regulating valve (27) and an eighth isolation valve (18);
the rear end of the eighth isolation valve (18) of the second steam transmission pipeline (33) is provided with a first attemperator (24);
the steam supply pipeline (36) and the second steam transmission pipeline (33) are communicated with the shaft seal pipeline (35) through a tee joint; the shaft seal pipeline (35) is provided with a first branch (37) and a second branch (38) which are communicated; the first branch (37) is communicated with a high-pressure cylinder high-pressure side bearing seal (6) of the shaft seal structure (10); the second branch (38) is communicated with other positions of the shaft seal structure (10) through the branch.
2. The high-temperature gas cooled reactor shaft seal steam supply system according to claim 1, wherein an outlet converging pipeline (30) is communicated with the outlet of the steam generator (1); a seventh isolation valve (17) is arranged on the outlet converging pipeline (30); one end of the outlet converging pipeline (30) far away from the steam generator (1) is communicated with the steam exhaust pipeline (31) and the starting end of the first steam transmission pipeline (32) through a tee joint.
3. The high-temperature gas cooled reactor shaft seal steam supply system according to claim 1, wherein two ends of the second isolation valve (12) and the eighth isolation valve (18) of the second steam transmission pipeline (33) are respectively communicated with two ends of the first bypass pipeline (42).
4. A high temperature gas cooled reactor shaft seal steam supply system according to claim 3, characterized in that the first bypass line (42) is provided with a ninth isolation valve (19).
5. The high temperature gas cooled reactor shaft seal steam supply system according to claim 1, wherein a second desuperheater (25) is arranged on the second branch (38).
6. The high-temperature gas cooled reactor shaft seal steam supply system according to claim 1, wherein two ends of a sixth isolation valve (16) and a tenth isolation valve (20) of the steam supply pipeline (36) are respectively communicated with two ends of a second bypass pipeline (43); an eleventh isolation valve (21) is arranged on the second bypass pipeline (43).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111301561.1A CN113982700B (en) | 2021-11-04 | 2021-11-04 | High-temperature gas cooled reactor shaft seal steam supply system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111301561.1A CN113982700B (en) | 2021-11-04 | 2021-11-04 | High-temperature gas cooled reactor shaft seal steam supply system |
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| Publication Number | Publication Date |
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| CN113982700A CN113982700A (en) | 2022-01-28 |
| CN113982700B true CN113982700B (en) | 2023-11-21 |
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| CN202111301561.1A Active CN113982700B (en) | 2021-11-04 | 2021-11-04 | High-temperature gas cooled reactor shaft seal steam supply system |
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| 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 |
| CN110159360A (en) * | 2019-06-11 | 2019-08-23 | 中国电力工程顾问集团西北电力设计院有限公司 | A kind of Gas-steam Combined Cycle power plant shaft seal steam supply system and steam supplying method |
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| CN113431638A (en) * | 2021-06-21 | 2021-09-24 | 华能山东石岛湾核电有限公司 | High-temperature gas cooled reactor shaft seal system and rapid gas supply device and method thereof |
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2021
- 2021-11-04 CN CN202111301561.1A patent/CN113982700B/en active Active
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| JPH06299803A (en) * | 1993-04-13 | 1994-10-25 | Toshiba Eng Co Ltd | Bypass method of gland sealing steam system of steam turbine |
| JPH09280005A (en) * | 1996-04-09 | 1997-10-28 | Fuji Electric Co Ltd | Shaft sealing device of steam turbine |
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| Publication number | Publication date |
|---|---|
| CN113982700A (en) | 2022-01-28 |
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