CN203376984U - Isolating system used for shaft-seal leakage pipeline of cooling agent pump - Google Patents
Isolating system used for shaft-seal leakage pipeline of cooling agent pump Download PDFInfo
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- CN203376984U CN203376984U CN201320448546.4U CN201320448546U CN203376984U CN 203376984 U CN203376984 U CN 203376984U CN 201320448546 U CN201320448546 U CN 201320448546U CN 203376984 U CN203376984 U CN 203376984U
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- 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 utility model belongs to the accident condition processing technology of a nuclear power station and specifically discloses an isolating system used for a shaft-seal leakage pipeline of a cooling agent pump. The isolating system comprises a low-voltage leakage parallel-connection pipeline and a high-voltage leakage parallel-connection pipeline, wherein the low-voltage leakage parallel-connection pipeline comprises a second steam-driven isolating valve and a fourth electric valve which are in parallel connected; the high-voltage leakage parallel-connection pipeline comprises a first steam-driven isolating valve and a second electric valve which are parallel; one end of the low-voltage leakage parallel-connection pipeline is connected with an RPE system; the other end of the low-voltage leakage parallel-connection pipeline is connected with a third electrically-operated valve and a main pump shaft sealing system; one end of the high-voltage leakage parallel-connection pipeline is connected with an RCV (Removal-Chemical and Volume) system; the other end of the high-voltage leakage parallel-connection pipeline is connected with the first electrically operated valve and the main pump shaft sealing system. Under an accident condition of losing a power supply, the shaft-seal system is effectively isolated, so that a primary circuit coolant is not leaked through the shaft-seal leakage pipeline, thereby keeping integrity of a primary circuit boundary and avoiding the primary circuit loss caused by shaft-seal leakage.
Description
Technical field
The utility model belongs to nuclear power plant accident operating mode treatment technology, is specifically related to a kind of shielding system.
Background technology
Shaft seal assembly or the system of presurized water reactor shaft seal formula reactor coolant pump (abbreviation main pump) provide the pressure isolation from reactor coolant loop pressure to environmental baseline, thereby prevent that reactor coolant from leaking to environment, be critical component on the integrality that guarantees pressure-bearing boundary.Under nominal situation, from the shaft seal injected water of RCV system with higher than the RCP(reactor coolant loop) in system absolute pressure injection pump, in this injected water, a part flows downward after the cooling water lubrication guide bearing and enters the RCP(reactor coolant loop) in system, to prevent that the circuit cools agent from entering pump bearing and shaft seal district, the injected water of remaining another part returns to respectively the RCV(cvcs after by restriction device and sealing surface) system and RPE(nuclear island drain and vent system) system.
In the station blackout situation, nuclear power plant has lost all power that comprises the interior emergent generator powered of power supply and field outside factory.Lose all power after a period of time in nuclear power plant, main pump injects and the component cooling water supply owing to having lost shaft seal water, one circuit cools agent meeting of High Temperature High Pressure upwards enters axle sealing system, and finally the leakage line by sealing lets out, and causes a loop dehydration.
After third generation million kilowatt nuclear power stands in the station blackout accident operating mode, do not occur in 72 hours to leak and cause a loop loss of-coolant accident (LOCA) due to sealing, retainer shaft sealing at least 72 hours is complete.Need a kind of shielding system, under the station blackout operating mode, axle sealing system and the external world are isolated guaranteeing, guarantee the complete of sealing under the station blackout operating mode, avoid because one loop loss of-coolant accident (LOCA) occurs in the main pump shaft seal leakage.
Adopt the nuclear power station of three grades of hydrodynamic seal main pumps that this sealing leakage shielding system be comprised of isolation pipeline and valve is not set in the past, in losing factory's dispatch from foreign news agency and factory, under the station blackout accident operating mode of emergency power pack, can't guarantee the complete of sealing.
Summary of the invention
The purpose of this utility model is to provide a kind of shielding system for cooling medium pump sealing leakage line, can guarantee under the station blackout operating mode, axle sealing system and the external world to be isolated, guarantee the integrality of sealing under the station blackout operating mode, avoid because one loop loss of-coolant accident (LOCA) occurs in the main pump shaft seal leakage.
The technical solution of the utility model is as follows:
A kind of shielding system for cooling medium pump sealing leakage line, comprise low-pressure leak parallel pipeline and high-pressure leakage parallel pipeline; Described low-pressure leak parallel pipeline comprises the second steam-operating isolation valve and the 4th motorized valve in parallel; Described high-pressure leakage parallel pipeline comprises the first steam-operating isolation valve and the second motorized valve in parallel; One end of described low-pressure leak parallel pipeline connects the RPE system, and the other end connects the 3rd motorized valve and main pump shaft sealing system successively by pipeline; One end of described high-pressure leakage parallel pipeline connects the RCV system, and an end connects the first motorized valve and main pump shaft sealing system successively by pipeline.
In the above-mentioned shielding system for cooling medium pump sealing leakage line: described the first motorized valve, the second motorized valve, the 3rd motorized valve and the 4th motorized valve are French VELAN or the valve DN25 of center Soviet Union motorized valve.
In the above-mentioned shielding system for cooling medium pump sealing leakage line: the first steam-operating isolation valve and the second steam-operating isolation valve are French VELAN or the valve DN25 of center Soviet Union isolation valve.
The beneficial effects of the utility model are: losing under the accident conditions of power supply, axle sealing system has been implemented to effective isolation, one circuit cools agent can not leaked by the sealing leakage line, kept the complete of a border, loop, avoided because one loop dehydration occurs in the sealing leakage; Dehydration can not occur because of shaft sealing leakage in next loop of the accident conditions that loses power supply, this is effectively to take away the precondition of a loop reactor core heat release after secondary side auxiliary feedwater system and Heat Discharging System of Chinese drop into; Even steam-operating isolation valve mistake is closed, the motorized valve of Parallel Design is opened also can guarantee the stable operation of main pump unit; The pipeline adopted and valve are nuclear safety I level, and its supplier is ripe supplier, have good supply of material achievement, the reliability of assurance system self.
The accompanying drawing explanation
Fig. 1 is the shielding system schematic diagram for cooling medium pump sealing leakage line;
In figure: 1. the first motorized valve; 2. the first steam-operating isolation valve; 3. the second motorized valve; 4. the 3rd motorized valve; 5. the second steam-operating isolation valve; 6. the 4th motorized valve; 7. pipeline.
Embodiment
Below in conjunction with drawings and the specific embodiments, the utility model is described in further detail.
The steam-operating isolation valve of selecting in the utility model is selected the DN25 of French VELAN or center Soviet Union valve, and this valve is nuclear safety I level, and design pressure is 17.23MP, and design temperature is 343 ℃, and valve body is Austenitic stainless steel forging, belongs to a loop pressure-bearing boundary.
The motorized valve of selecting in the utility model is selected the DN25 motorized valve of French VELAN or center Soviet Union valve, and this valve is nuclear safety I level, and design pressure is 17.23MP, and design temperature is 343 ℃, and valve body is Austenitic stainless steel forging, belongs to a loop pressure-bearing boundary.
The pipeline that the utility model is selected is the DN25 high pressure line, and this pipe design pressure is 17.23MPa, and design temperature is 343 ℃
As shown in Figure 1, junction line 7, four motorized valves and two steam-operating isolation valves, consist of, wherein the first steam-operating isolation valve 2 and the second motorized valve 3 are that high pressure is revealed the pipeline isolation valve, and the second steam-operating isolation valve 5 and the 4th motorized valve 6 are low-pressure leak pipeline isolation valve.
The second steam-operating isolation valve 5 and the 4th motorized valve 6 are connected in parallel, and form the low-pressure leak parallel pipeline, and an end of low-pressure leak parallel pipeline connects the RPE system, the 3rd motorized valve 4 is installed on the pipeline 7 of the other end, and is connected to the main pump shaft sealing system.
The first steam-operating isolation valve 2 and the second motorized valve 3 are connected in parallel, and form the high-pressure leakage parallel pipeline, and an end of high-pressure leakage parallel pipeline connects the RCV system, the first motorized valve 1 is installed on the pipeline 7 of the other end, and is connected to the main pump shaft sealing system.
Under nominal situation, the sealing injected water is flowed through after the first motorized valve 1, the 3rd motorized valve 4 and the first steam-operating isolation valve 2 opened, the second steam-operating isolation valve 5 and is returned to respectively RCV and RPE system by its leakage line after sealing.Under whole audience outage operating mode, the first motorized valve 1, the 3rd motorized valve 4 can't be closed, and be set to the first steam-operating isolation valve 2 and the second steam-operating isolation valve 5 that dead electricity closes, realize closing isolation.
Under nominal situation, from the shaft seal injected water of RCV system with higher than in RCP system absolute pressure injection pump, in this injected water, a part flows downward after the cooling water lubrication guide bearing and enters in the RCP system, to prevent that the circuit cools agent from entering pump bearing and shaft seal district, the injected water of remaining another part is flowed through and is returned to respectively RCV system and RPE system (the high and low pressure leakage line is passed through flange connect with the pipeline be arranged in shaft sealing chamber) by high-pressure leakage pipeline and low-pressure leak pipeline after restriction device and sealing surface.Therefore the leakage line of main pump shaft sealing can not be isolated under nominal situation, the isolation valve on leakage line must be held open state.
Station blackout (comprise outside factory power supply and in all power of emergent generator powered) accident is while occurring, and for guaranteeing a loop, loss of-coolant accident (LOCA) do not occur, the leakage line that main pump shaft seals must be closed isolation.
Claims (3)
1. the shielding system for cooling medium pump sealing leakage line, is characterized in that: comprise low-pressure leak parallel pipeline and high-pressure leakage parallel pipeline; Described low-pressure leak parallel pipeline comprises the second steam-operating isolation valve (5) and the 4th motorized valve (6) in parallel; Described high-pressure leakage parallel pipeline comprises the first steam-operating isolation valve (2) and the second motorized valve (3) in parallel; One end of described low-pressure leak parallel pipeline connects the RPE system, and the other end connects the 3rd motorized valve (4) and main pump shaft sealing system successively by pipeline (7); One end of described high-pressure leakage parallel pipeline connects the RCV system, and an end connects the first motorized valve (1) and main pump shaft sealing system successively by pipeline (7).
2. the shielding system for cooling medium pump sealing leakage line as claimed in claim 1 is characterized in that: described the first motorized valve (1), the second motorized valve (3), the 3rd motorized valve (4) and the 4th motorized valve (6) are French VELAN or the valve DN25 of center Soviet Union motorized valve.
3. the shielding system for cooling medium pump sealing leakage line as claimed in claim 1 is characterized in that: the first steam-operating isolation valve (2) and the second steam-operating isolation valve 5 are French VELAN or the valve DN25 of center Soviet Union isolation valve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201320448546.4U CN203376984U (en) | 2013-07-25 | 2013-07-25 | Isolating system used for shaft-seal leakage pipeline of cooling agent pump |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201320448546.4U CN203376984U (en) | 2013-07-25 | 2013-07-25 | Isolating system used for shaft-seal leakage pipeline of cooling agent pump |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN203376984U true CN203376984U (en) | 2014-01-01 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201320448546.4U Expired - Lifetime CN203376984U (en) | 2013-07-25 | 2013-07-25 | Isolating system used for shaft-seal leakage pipeline of cooling agent pump |
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|---|---|
| CN (1) | CN203376984U (en) |
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104733059A (en) * | 2015-03-30 | 2015-06-24 | 中广核工程有限公司 | Main pump shaft seal pressure balancing device and method for nuclear power station |
| CN105448367A (en) * | 2014-08-19 | 2016-03-30 | 中国广核集团有限公司 | Method for treating nuclear power station main pump leakage abnormity |
| CN106870441A (en) * | 2015-12-11 | 2017-06-20 | 中广核工程有限公司 | Nuclear power station main pump axle envelope injects water system |
| CN108731501A (en) * | 2017-10-25 | 2018-11-02 | 江苏核电有限公司 | Energy saver and power-economizing method for the optimization of vacuum water-jet pump system operation mode |
| CN110491532A (en) * | 2019-07-25 | 2019-11-22 | 岭澳核电有限公司 | Nuclear power station main pump abnormal leakage processing system and method |
| CN112681447A (en) * | 2021-01-06 | 2021-04-20 | 三门核电有限公司 | Nuclear power station plant water pump shaft seal water supply system |
| CN112682327A (en) * | 2020-12-24 | 2021-04-20 | 中广核核电运营有限公司 | Main pump overhauling method |
-
2013
- 2013-07-25 CN CN201320448546.4U patent/CN203376984U/en not_active Expired - Lifetime
Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105448367A (en) * | 2014-08-19 | 2016-03-30 | 中国广核集团有限公司 | Method for treating nuclear power station main pump leakage abnormity |
| CN105448367B (en) * | 2014-08-19 | 2017-09-08 | 中国广核集团有限公司 | The processing method of nuclear power station main pump abnormal leakage |
| CN104733059A (en) * | 2015-03-30 | 2015-06-24 | 中广核工程有限公司 | Main pump shaft seal pressure balancing device and method for nuclear power station |
| CN104733059B (en) * | 2015-03-30 | 2017-10-31 | 中广核工程有限公司 | A kind of nuclear power station main pump axial seal pressure bascule and method |
| CN106870441A (en) * | 2015-12-11 | 2017-06-20 | 中广核工程有限公司 | Nuclear power station main pump axle envelope injects water system |
| CN106870441B (en) * | 2015-12-11 | 2019-01-15 | 中广核工程有限公司 | Nuclear power station main pump axle envelope injects water system |
| CN108731501A (en) * | 2017-10-25 | 2018-11-02 | 江苏核电有限公司 | Energy saver and power-economizing method for the optimization of vacuum water-jet pump system operation mode |
| CN110491532A (en) * | 2019-07-25 | 2019-11-22 | 岭澳核电有限公司 | Nuclear power station main pump abnormal leakage processing system and method |
| CN110491532B (en) * | 2019-07-25 | 2021-07-06 | 岭澳核电有限公司 | Nuclear power station main pump leakage abnormity processing system and method |
| CN112682327A (en) * | 2020-12-24 | 2021-04-20 | 中广核核电运营有限公司 | Main pump overhauling method |
| CN112682327B (en) * | 2020-12-24 | 2022-05-24 | 中广核核电运营有限公司 | Main pump overhauling method |
| CN112681447A (en) * | 2021-01-06 | 2021-04-20 | 三门核电有限公司 | Nuclear power station plant water pump shaft seal water supply system |
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| Date | Code | Title | Description |
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| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CX01 | Expiry of patent term | ||
| CX01 | Expiry of patent term |
Granted publication date: 20140101 |