CN203026165U - Circuit accident exhaust system of pressurized water reactor nuclear power plant - Google Patents
Circuit accident exhaust system of pressurized water reactor nuclear power plant Download PDFInfo
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- CN203026165U CN203026165U CN2012206862323U CN201220686232U CN203026165U CN 203026165 U CN203026165 U CN 203026165U CN 2012206862323 U CN2012206862323 U CN 2012206862323U CN 201220686232 U CN201220686232 U CN 201220686232U CN 203026165 U CN203026165 U CN 203026165U
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- nuclear power
- solenoid valve
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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
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Abstract
The utility model discloses an accident responding system of a pressurized water reactor nuclear power plant and in particular relates to a circuit accident exhaust system of a pressurized water reactor nuclear power plant. The circuit accident exhaust system of the pressurized water reactor nuclear power plant comprises accident exhaust valves connected between a reactor pressure container and a normal exhaust valve; the accident exhaust valves are divided into two series; a series of normally-closed accident exhaust valves are guided out from the top of the reactor pressure container and connected in parallel; a series A of the accident exhaust valves are composed of a first normally-closed solenoid valve and a second normally-closed solenoid valve in series connection; and a series B of the accident exhaust valves are composed of a third normally-closed solenoid valve and a fourth normally-closed solenoid valve in serial connection and connected in parallel to a safety valve discharging pipeline of the pressure stabilizer to enter a pressure relieving tank. The circuit accident exhaust system disclosed by the utility model has the advantage that the system adopting solenoid valves is stable and reliable in performance and fast in action, can be used for effectively alleviating the serious accident consequences and ensuring the completeness of the reactor pressure container in the serious accidents.
Description
Technical field
The invention belongs to a kind of accident answering system of PWR nuclear power plant, be specifically related to a kind of PWR nuclear power plant one loop accident exhaust system.
Background technology
One loop accident exhaust is a kind of severe accident relieving measure.Under accident conditions, the accident exhaust system puts into operation, discharges the non-condensable gas that the reactor pressure vessel top is gathered, thereby prevents the impact that these not concretive gas conduct heat on reactor core, guarantee to only have unique carbonated drink interface in reactor coolant loop, alleviate damage sequence.
Domestic two generations added nuclear power station in the past only the normal exhaust system, only the power station start-up course or reload forward and backward, manually to the reactor coolant loop exhaust, in order to system is carried out relevant water-filling operation.Under accident conditions, can't discharge incoagulable gas of reactor pressure vessel the inside, affect the heat transfer of reactor core.
Summary of the invention
the purpose of this invention is to provide a kind of PWR nuclear power plant one loop accident exhaust system, under accident conditions, can produce a large amount of incoagulability gas in reactor pressure vessel, these gases can accumulate in the reactor pressure vessel top, when needs are discharged these incoagulability gases, by operator according to corresponding signal and malfunction protocol at the manually opened accident vent valve of main control room, the non-condensable gas that discharge reactor pressure vessel top is gathered, thereby prevent that these not concretive gas are on the impact of a kind of PWR nuclear power plant one loop accident method for exhausting of reactor core, guarantee to only have unique carbonated drink interface in reactor coolant loop, alleviate damage sequence.
The present invention is achieved in that a kind of PWR nuclear power plant one loop accident exhaust system, and it comprises the accident vent valve that is connected between reactor pressure vessel and normal exhaust valve.
Described accident vent valve is divided into two series, from the reactor pressure vessel Base top contact, through the normal pass of two parallel connections series, first normal pass solenoid valve is connected with second normal pass solenoid valve and is consisted of series A, the 3rd normal pass solenoid valve connected with the 4th normal pass solenoid valve and consisted of serial B, and the pressurizer safety valve bleeder line that accesses in parallel enters the release case.
Advantage of the present invention is that this system takes solenoid valve, and is stable and reliable for performance, is swift in motion, and can effectively alleviate the major accident consequence, guarantees the integrality of reactor pressure vessel under major accident.
Description of drawings
Fig. 1 is a kind of PWR nuclear power plant one loop accident exhaust system schematic diagram provided by the present invention.
In figure, 1 reactor pressure vessel, 2 normal exhaust valves, 3 accident vent valves, 4 nuclear island exhaust and draining systems, 5 release casees, 6 first normal solenoid valves that close, 7 second normal solenoid valves that close, 8 the 3rd normal solenoid valves that close, 9 the 4th normal solenoid valves that close.
Embodiment
Below in conjunction with drawings and Examples, the present invention is described in detail:
" PWR nuclear power plant one loop accident exhaust system " by unlatching accident vent valve, with accumulating in the incoagulability gas discharge reactor pressure vessel at reactor pressure vessel top, alleviates damage sequence when having an accident.
A kind of PWR nuclear power plant one loop accident exhaust system, it comprises by pipeline and is connected to accident vent valve 3 between reactor pressure vessel 1 and normal exhaust valve 2, wherein accident vent valve 3 is divided into two series, from the reactor pressure vessel Base top contact, through the normal pass of two parallel connections series, it is first normal solenoid valve 6 and second normal solenoid valve 7 formation series A of connecting that closes of closing, the 3rd normal pass solenoid valve 8 connected with the 4th normal pass solenoid valve 9 and consisted of serial B, access pressurizer safety valve bleeder line in parallel, enter release case 5 at last afterwards.
The accident vent valve: during normal reactor operation, this valve closing is the isolation valve on a border, loop; During accident, open this valve, discharge the non-condensable gas at reactor pressure vessel top.
When unit normally moved, the accident exhaust system was standby, and the accident vent valve is in closed condition.Under accident conditions, can produce a large amount of incoagulability gas in reactor pressure vessel, these gases can accumulate in the reactor pressure vessel top, affect the heat transfer of reactor core.
When needs are discharged these incoagulability gases, by operator according to corresponding signal and the malfunction protocol accident vent valve in manually opened two series of main control room, with accumulating in the incoagulability gas discharge reactor pressure vessel at reactor pressure vessel top, alleviate damage sequence.
Claims (2)
1. PWR nuclear power plant one loop accident exhaust system, it is characterized in that: it comprises the accident vent valve (3) that is connected between reactor pressure vessel (1) and normal exhaust valve (2).
2. a kind of PWR nuclear power plant one loop accident exhaust system as claimed in claim 1, it is characterized in that: described accident vent valve (3) is divided into two series, from the reactor pressure vessel Base top contact, through the normal pass of two parallel connections series, first normal pass solenoid valve (6) is connected with second normal pass solenoid valve (7) and is consisted of series A, the 3rd normal pass solenoid valve (8) connected with the 4th normal pass solenoid valve (9) and consisted of serial B, and the pressurizer safety valve bleeder line that accesses in parallel enters release case (5).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012206862323U CN203026165U (en) | 2012-12-13 | 2012-12-13 | Circuit accident exhaust system of pressurized water reactor nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012206862323U CN203026165U (en) | 2012-12-13 | 2012-12-13 | Circuit accident exhaust system of pressurized water reactor nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN203026165U true CN203026165U (en) | 2013-06-26 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2012206862323U Expired - Lifetime CN203026165U (en) | 2012-12-13 | 2012-12-13 | Circuit accident exhaust system of pressurized water reactor nuclear power plant |
Country Status (1)
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| CN (1) | CN203026165U (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103390435A (en) * | 2013-07-30 | 2013-11-13 | 中广核工程有限公司 | Exhaust device and method for pressure vessel of nuclear power plant reactor coolant system |
| CN103400607A (en) * | 2013-07-31 | 2013-11-20 | 中广核工程有限公司 | Vacuumizing method for reactor coolant system of nuclear power plant |
| CN103871504A (en) * | 2012-12-13 | 2014-06-18 | 中国核动力研究设计院 | Pressurized water reactor nuclear power plant circuit accident gas exhaust system |
| CN103985422A (en) * | 2014-03-20 | 2014-08-13 | 中国核动力研究设计院 | Active and passive nuclear steam supplying system based on 177 reactor core and nuclear power station thereof |
-
2012
- 2012-12-13 CN CN2012206862323U patent/CN203026165U/en not_active Expired - Lifetime
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103871504A (en) * | 2012-12-13 | 2014-06-18 | 中国核动力研究设计院 | Pressurized water reactor nuclear power plant circuit accident gas exhaust system |
| WO2014090142A1 (en) * | 2012-12-13 | 2014-06-19 | 中国核动力研究设计院 | Circuit accident exhaust system of pressurized water reactor nuclear power plant |
| CN103390435A (en) * | 2013-07-30 | 2013-11-13 | 中广核工程有限公司 | Exhaust device and method for pressure vessel of nuclear power plant reactor coolant system |
| CN103390435B (en) * | 2013-07-30 | 2016-08-24 | 中广核工程有限公司 | The exhaust apparatus of nuclear power plant reactor coolant system pressure vessel and method |
| CN103400607A (en) * | 2013-07-31 | 2013-11-20 | 中广核工程有限公司 | Vacuumizing method for reactor coolant system of nuclear power plant |
| CN103400607B (en) * | 2013-07-31 | 2016-01-06 | 中广核工程有限公司 | Nuclear power plant reactor coolant system vacuum pumping method |
| CN103985422A (en) * | 2014-03-20 | 2014-08-13 | 中国核动力研究设计院 | Active and passive nuclear steam supplying system based on 177 reactor core and nuclear power station thereof |
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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: 20130626 |