CN203397706U - Nuclear power station pressure vessel accident exhaust system - Google Patents
Nuclear power station pressure vessel accident exhaust system Download PDFInfo
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- CN203397706U CN203397706U CN201320509541.8U CN201320509541U CN203397706U CN 203397706 U CN203397706 U CN 203397706U CN 201320509541 U CN201320509541 U CN 201320509541U CN 203397706 U CN203397706 U CN 203397706U
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- pass valve
- pipeline
- accident
- pressure vessel
- valve control
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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 a nuclear power station pressure vessel accident exhaust system. The nuclear power station pressure vessel accident exhaust system comprises a pressure vessel (1); the nuclear power station pressure vessel accident exhaust system also comprises an accident exhaust device (2) used for discharging the gas gathered in the pressure vessel (1), and a pressure relief device (3); one end of the accident exhaust device (2) is communicated with the top of the pressure vessel (1), and the other end of the accident exhaust device (2) is communicated with the pressure relief device (3). The nuclear power station pressure vessel accident exhaust system has the beneficial effects that under the accident condition, the gas gathered on the top of the pressure vessel is discharged into the pressure relief device through the accident exhaust device, so that the gas gathered on the top of the pressure vessel can be discharged in time, and the capability of the dealing with the beyond design basis accidents of a nuclear power station can be improved.
Description
Technical field
The utility model relates to the compressed water reactor nuclear power unit of nuclear power station, more particularly, relates to a kind of nuclear plant pressure vessels accident exhaust system.
Background technology
In the compressed water reactor nuclear power unit of nuclear power station, pressure vessel is built-in with reactor core.In some accident (as beyond design basis accident, major accident etc.) process and post incident, heap in-core may produce a large amount of gathering gas (water vapour and/or not condensable gas), wherein a part is assembled gas buildup at pressure vessel top, may bring following adverse effect like this:
-affecting reactor core conducts heat;
The Natural Circulation of-destruction reactor coolant;
In-coolant system, there are two free interfaces, affect system unload and water-filling again.
In prior art, as shown in Figure 1, pressure vessel 100 tops at reactor are provided with exhaust line 200, hand valve 300 and blind flange 400 are set on exhaust line 200, in the normal startup of unit and stoppage in transit, fill in drainage procedure, by operator, manually remove blind flange 400, by flexible pipe, be connected to RPE system (nuclear island exhaust and draining system), open again hand valve 300, the exhaust at realization response core pressure vessel top.
But such scheme of the prior art, the function that only possesses shutdown maintenance and the front and back normal exhaust of reloading, still do not possess the ability that under accident conditions, gas is assembled in discharge, under accident conditions, the uncontrollable hand valve 300 of operator is opened and dismounting blind flange 400, can not carry out reactor pressure vessel top degassing function.
To sum up, there is following defect in pressure vessel of the prior art: when accident conditions, pressure vessel can not discharge gathering gas.
Utility model content
The technical problems to be solved in the utility model is, for the above-mentioned defect of prior art, provide a kind of when accident conditions can by accident exhaust apparatus by the gathering gas discharging in pressure vessel the nuclear plant pressure vessels accident exhaust system to pressure relief device.
The utility model solves the technical scheme that its technical matters adopts: construct a kind of nuclear plant pressure vessels accident exhaust system, comprise pressure vessel, described nuclear plant pressure vessels accident exhaust system also comprises accident exhaust apparatus and the pressure relief device of assembling gas in described pressure vessel for discharging, and described accident exhaust apparatus one end is connected with the top of described pressure vessel, the described accident exhaust apparatus other end is connected with described pressure relief device.
In nuclear plant pressure vessels accident exhaust system described in the utility model, described accident exhaust apparatus comprises the first pipeline, on described the first pipeline, be provided with at least one the first by-pass valve control, described pressure vessel and described pressure relief device are connected by described the first pipeline.
In nuclear plant pressure vessels accident exhaust system described in the utility model, described accident exhaust apparatus also comprises the second pipeline, on described the second pipeline, be provided with at least one the second by-pass valve control, described the second pipeline and described the first pipeline are in parallel, and at least one described the first by-pass valve control and at least one described the second by-pass valve control are and are arranged in parallel.
In nuclear plant pressure vessels accident exhaust system described in the utility model, described accident exhaust apparatus also comprises control system, described the first by-pass valve control and described the second by-pass valve control are electrically connected to described control system respectively, described control system for control described the first by-pass valve control and described the second by-pass valve control unlatching or close.
In nuclear plant pressure vessels accident exhaust system described in the utility model, on described the first pipeline, be also provided with at least one the first thermometer and/or at least one the first pressure gauge, on described the second pipeline, be also provided with at least one the second thermometer and/or at least one the second pressure gauge; Described the first thermometer, described the first pressure gauge, described the second thermometer and described the second pressure gauge are connected with described control system respectively.
In nuclear plant pressure vessels accident exhaust system described in the utility model, on described the first pipeline, be also provided with at least one the first restrictor and/or described the second pipeline and be also provided with at least one the second restrictor.
In nuclear plant pressure vessels accident exhaust system described in the utility model, described pressure vessel top is connected with exhaust line, away from the end of the described exhaust line of described pressure vessel, is connected with blind flange, and hand valve is also installed on described exhaust line.
In nuclear plant pressure vessels accident exhaust system described in the utility model, the described exhaust line between described pressure vessel and described hand valve is connected with described accident exhaust apparatus.
In nuclear plant pressure vessels accident exhaust system described in the utility model, the quantity of described the first by-pass valve control is 2, and the quantity of described the second by-pass valve control is 2; Described the first by-pass valve control is solenoid valve or motorized valve or pneumatic valve, and described the second by-pass valve control is solenoid valve or motorized valve or pneumatic valve.
In nuclear plant pressure vessels accident exhaust system described in the utility model, described pressure relief device comprises pressurizer relief tank.
Implement nuclear plant pressure vessels accident exhaust system of the present utility model, there is following beneficial effect: when accident conditions, in pressure vessel, be gathered in the gas at top, by accident exhaust apparatus, be disposed to pressure relief device, the gas that pressure vessel top can be assembled is like this discharged in time, be conducive to Core cooling, recover reactor core water level and recover a loop natural circulation, increase the safety coefficient of reactor, also improved the ability of nuclear power station reply beyond design basis accident.
Accompanying drawing explanation
Below in conjunction with drawings and Examples, the utility model is described in further detail, in accompanying drawing:
Fig. 1 is the structural representation that in prior art, pressure vessel top arranges exhaust line;
Fig. 2 is the structural representation of the utility model nuclear plant pressure vessels accident exhaust system the first embodiment;
Fig. 3 is the structural representation of the utility model nuclear plant pressure vessels accident exhaust system the second embodiment;
Fig. 4 is the structural representation of the utility model nuclear plant pressure vessels accident exhaust system the 3rd embodiment;
Fig. 5 is the structural representation of the utility model nuclear plant pressure vessels accident exhaust system the 4th embodiment;
Fig. 6 is the structural representation of the utility model nuclear plant pressure vessels accident exhaust system the 5th embodiment;
Fig. 7 is the structural representation of the utility model nuclear plant pressure vessels accident exhaust system the 6th embodiment;
Fig. 8 is the logic diagram of the utility model nuclear plant pressure vessels accident exhaust system embodiment;
In Fig. 1: 100-pressure vessel, 200-exhaust line, 300-hand valve, 400-blind flange;
In Fig. 2-Fig. 8:
1-pressure vessel; 11-exhaust line, 12-blind flange, 13-hand valve;
2-accident exhaust apparatus; 201-the first pipeline, 202-the first by-pass valve control, 203-the second pipeline, 204-the second by-pass valve control, 205-control system, 206-the first thermometer, 207-the first pressure gauge, 208-the second thermometer, 209-the second pressure gauge, 210-the first restrictor, 211-the second restrictor;
3-pressure relief device.
Embodiment
For technical characterictic of the present utility model, object and effect being had more clearly, understand, now contrast accompanying drawing and describe embodiment of the present utility model in detail.
Embodiment 1
As shown in Figure 2, the nuclear plant pressure vessels accident exhaust system of the present embodiment, comprise pressure vessel 1, nuclear plant pressure vessels accident exhaust system also comprises for the accident exhaust apparatus 2 of the interior gathering gas of discharge pressure container 1 and pressure relief device 3, and accident exhaust apparatus 2 one end are connected with the top of pressure vessel 1, accident exhaust apparatus 2 other ends are connected with pressure relief device 3.Assemble gas and be for example water vapour and/or condensable gas not.
Pressure vessel 1 top is connected with exhaust line 11, away from the exhaust line 11 end of pressure vessel 1, is connected with blind flange 12, and hand valve 13 is also installed on exhaust line 11.The connected mode of exhaust line 11 and pressure vessel 1 is such as being that welding or securing member are connected etc., and exhaust line 11, for removably connecting for example, is connected by screw with the connected mode of blind flange 12.
In process in shutdown maintenance and before and after reloading, can carry out exhaust by exhaust line 11, detailed process is: by operator, manually remove blind flange 12, by flexible pipe, be connected to RPE system (nuclear island exhaust and draining system), open again hand valve 13, the exhaust at realization response core pressure vessel top.When accident conditions, by the nuclear plant pressure vessels accident exhaust system of the present embodiment, carry out exhaust.By exhaust line 11, carry out the mode of exhaust and carry out exhaust by the nuclear plant pressure vessels accident exhaust system of the present embodiment not interfereing with each other, all can independently carry out.
In the present embodiment, exhaust line 11 between pressure vessel 1 and hand valve 13 is connected with accident exhaust apparatus 2, further, the exhaust line 11 between pressure vessel 1 and hand valve 13 is connected with the first pipeline 201, and the connected mode of exhaust line 11 and the first pipeline 201 is for example welding.Certainly, in certain embodiments, the first pipeline 201 can not be connected with exhaust line 11 yet, but the first pipeline 201 is directly connected to the top of pressure vessel 1, and other is identical with the present embodiment.
In the present embodiment, be provided with preferably solenoid valve of 2 the first by-pass valve control 202, the first by-pass valve controls 202 on the first pipeline 201, the first by-pass valve control 202 can be also motorized valve or pneumatic valve in other embodiments.On the first pipeline 201, be provided with 2 the first by-pass valve controls 202 and be because: only open 2 the first by-pass valve controls 202 and just can carry out exhaust, if can avoid so only arranging the problem that 1 the first by-pass valve control 202 mistiming is opened, 2 the first by-pass valve controls 202 also can prevent the possibility of pressure vessel 1 interior reactor coolant leakage simultaneously, strengthen the reliability of isolation.Certainly, in certain embodiments, 1 the first by-pass valve control 202 also can be only set on the first pipeline 201, just now exist and open by mistake the risk that opens the first by-pass valve control 202; The first by-pass valve control 202 of the quantity such as 3 or 5 also can be set on the first pipeline 201, but now may increase operator's operation steps.
Consider that pressure vessel 1 top cannot integral arrangement the first by-pass valve control 202 and relevant distribution, Holder Fasteners, therefore accident exhaust apparatus 2 is arranged in outside reactor building, have enough arrangement space, and facilitate plant maintenance.
As shown in Figure 3, accident exhaust apparatus 2 also comprises the second pipeline 203, on the second pipeline 203, be provided with at least one the second by-pass valve control 204, the second pipelines 203 and the first pipeline 201 and be in parallel, and at least one the first by-pass valve control 202 and at least one the second by-pass valve control 204 are and are arranged in parallel.
Further, 2 the second by-pass valve controls 204 are set on the second pipeline 203,2 the second by-pass valve controls 204 be set on the second pipeline 203 be because: only open 2 the second by-pass valve controls 204 and just can carry out exhaust, if can avoid so only arranging the problem that 1 the second by-pass valve control 204 mistiming is opened, 2 the second by-pass valve controls 204 also can prevent the possibility of pressure vessel 1 interior reactor coolant leakage simultaneously, strengthen the reliability of isolation.Certainly, in certain embodiments, 1 the second by-pass valve control 204 also can be only set on the second pipeline 203, just now exist and open by mistake the risk that opens the second by-pass valve control 204; The second by-pass valve control 204 of the quantity such as 3 or 5 also can be set on the second pipeline 203, but now may increase operator's operation steps.
As shown in Figure 3, in the present embodiment, on the first pipeline 201, be also provided with on 2 the first thermometer 206, the second pipelines 203 and be also provided with 1 the second thermometer 208; Wherein, the second thermometer 208 is between 2 the second by-pass valve controls 204, and first first thermometer 206 is between 2 the first by-pass valve controls 202, and second the first thermometer 206 is positioned at the porch of pressure relief device 3.Certainly, in certain embodiments, the second thermometer 208 that the quantity such as 2,5 also can be set on the first thermometer 206, the second pipelines 203 of the quantity such as 1,3 also can be set on the first pipeline 201, other is identical with the present embodiment.The first thermometer 206 is set and can monitors the possible leakage of the first by-pass valve control 202, the second thermometer 208 is set and can monitors the possible leakage of the second by-pass valve control 204.
In the present embodiment, on the first pipeline 201, be also provided with 1 the first restrictor 210, the first restrictor 210 and be positioned at the front end near the first by-pass valve control 202 of pressure vessel 1.Certainly, the first restrictor 210 also can adopt orifice plate to replace in other embodiments; The quantity of the first restrictor 210 and position are also not limited to above-mentioned.
As shown in Figure 8, accident exhaust apparatus 2 also comprises control system 205, the first by-pass valve control 202 and the second by-pass valve control 204 are electrically connected to control system 205 respectively, control system 205 for control the first by-pass valve control 202 and the second by-pass valve control 204 unlatching or close.Control system 205 produces control signal, and the first by-pass valve control 202 reception control signals also carry out the action that corresponding valve is opened or valve closes; The second by-pass valve control 204 is so same.
The first thermometer 206 is connected with control system 205 respectively with the second thermometer 208.The second thermometer 208 is surveyed the temperature of the second pipeline 203 interior media and produces corresponding temperature signal, and control system 205 receives temperature signal and carries out corresponding temperature demonstration, and the first thermometer 206 is so same.
In the situation of the operating mode that has an accident, open 2 the first by-pass valve controls 202, and open 2 the second by-pass valve controls 204, it is certain that the gas of the gathering in pressure vessel 1 enters the first pipeline 201(by exhaust line 11, now hand valve 13 is in closed condition), the gas that the first pipeline 201 is assembled a part drains in the second pipeline 203, remaining gathering gas is still interior mobile at the first pipeline 201 simultaneously, when the gathering gas in the first pipeline 201 through the gathering gas in second the first by-pass valve control 202 and the second pipeline 203 after second the second by-pass valve control 204, two parts are assembled gas and are converged, drain into afterwards pressure relief device 3.Certainly, the second pipeline 203 and the first pipeline 201 are in parallel, because be like this redundancy structure, also also can open 2 the first by-pass valve controls 202 and close 2 the second by-pass valve controls 204 and carry out exhaust, also can be open 2 the second by-pass valve controls 204 and close 2 the first by-pass valve controls 202 and carry out exhaust, increase like this stability and the safety guarantee of system.
Other is identical with embodiment 1.
As shown in Figure 4, in the present embodiment, on the first pipeline 201, be provided with 1 the first thermometer 206 and 1 the first pressure gauge 207, the second pipeline 203 is provided with 1 the second pressure gauge 209.The first thermometer 206 is positioned at the porch of pressure relief device 3, and the first pressure gauge 207 is between 2 the first by-pass valve controls 202, and the second pressure gauge 209 is between 2 the second by-pass valve controls 204.
As shown in Figure 8, the first thermometer 206, the first pressure gauge 207 are connected with control system 205 respectively with the second pressure gauge 209.The first pressure gauge 207 is surveyed the pressure of the medium in the first pipeline 201 and produces corresponding pressure signal, and control system 205 receives pressure signal and carries out corresponding pressure demonstration, and the second pressure gauge 209 is so same.
Other is identical with embodiment 2.
Embodiment 4
As shown in Figure 5, in the present embodiment, on the first pipeline 201, be provided with 1 the first thermometer 206 and 1 the first pressure gauge 207, the second pipeline 203 is provided with 1 the second thermometer 208 and 1 the second pressure gauge 209.The first pressure gauge 207 is between 2 the first by-pass valve controls 202, and the second pressure gauge 209 is between 2 the second by-pass valve controls 204; In 2 the first by-pass valve controls 202, the first by-pass valve control 202 near pressure vessel 1 is first first by-pass valve control 202, the first by-pass valve control 202 near pressure relief device 3 is that second the first by-pass valve control 202, the first thermometer 206 is positioned at second the first by-pass valve control 202 exit; In 2 the second by-pass valve controls 204, the second by-pass valve control 204 near pressure vessel 1 is first second by-pass valve control 204, the second by-pass valve control 204 near pressure relief device 3 is that second the second by-pass valve control 204, the second thermometer 208 is positioned at second the second by-pass valve control 204 exit; The first thermometer 206 and the second thermometer 208 are and are arranged in parallel.
Other is identical with embodiment 2.
Embodiment 5
As shown in Figure 6, in the present embodiment, on the first pipeline 201, be provided with 1 the first thermometer 206, the second pipeline 203 and be provided with 1 the second thermometer 208.In 2 the first by-pass valve controls 202, the first by-pass valve control 202 near pressure vessel 1 is first first by-pass valve control 202, the first by-pass valve control 202 near pressure relief device 3 is that second the first by-pass valve control 202, the first thermometer 206 is positioned at second the first by-pass valve control 202 exit; In 2 the second by-pass valve controls 204, the second by-pass valve control 204 near pressure vessel 1 is first second by-pass valve control 204, the second by-pass valve control 204 near pressure relief device 3 is that second the second by-pass valve control 204, the second thermometer 208 is positioned at second the second by-pass valve control 204 exit; The first thermometer 206 and the second thermometer 208 are and are arranged in parallel.
In the present embodiment, on the first pipeline 201, be also provided with on 1 the first restrictor 210, the second pipeline 203 and be also provided with 1 the second restrictor 211.The first restrictor 210 is between 2 the first by-pass valve controls 202, and the second restrictor 211 is between 2 the second by-pass valve controls 204.Certainly, the quantity of the first restrictor 210 can be also other quantity such as 2,3 or 5, and it is above-mentioned that the first restrictor 210 position is also not limited to, and can be any position on the first pipeline 201.The quantity of the second restrictor 211 can be also other quantity such as 2,3 or 5, and it is above-mentioned that the second restrictor 211 position is also not limited to, and can be any position on the second pipeline 203.Restrictor can limit a loop reactor coolant leakage amount when pipeline breaking.
Other is identical with embodiment 2.
Embodiment 6
As shown in Figure 7, in the present embodiment, on the first pipeline 201, be provided with on 1 the first restrictor 210, the second pipeline 203 and be provided with 1 the second restrictor 211.It is second the second by-pass valve control 204 near the second by-pass valve control 204 of pressure relief device 3 that the second restrictor 211 is positioned at second the second by-pass valve control 204() rear end, it is second the first by-pass valve control 202 near the first by-pass valve control 202 of pressure relief device 3 that the first restrictor 210 is positioned at second the first by-pass valve control 202() rear end.Other is identical with embodiment 2.
By reference to the accompanying drawings embodiment of the present utility model is described above; but the utility model is not limited to above-mentioned embodiment; above-mentioned embodiment is only schematic; rather than restrictive; those of ordinary skill in the art is under enlightenment of the present utility model; not departing from the scope situation that the utility model aim and claim protect, also can make a lot of forms, within these all belong to protection of the present utility model.
Claims (10)
1. a nuclear plant pressure vessels accident exhaust system, comprise pressure vessel (1), it is characterized in that, described nuclear plant pressure vessels accident exhaust system also comprises accident exhaust apparatus (2) and the pressure relief device (3) of assembling gas in described pressure vessel (1) for discharging, and described accident exhaust apparatus (2) one end is connected with the top of described pressure vessel (1), described accident exhaust apparatus (2) other end is connected with described pressure relief device (3).
2. nuclear plant pressure vessels accident exhaust system according to claim 1, it is characterized in that, described accident exhaust apparatus (2) comprises the first pipeline (201), on described the first pipeline (201), be provided with at least one the first by-pass valve control (202), described pressure vessel (1) and described pressure relief device (3) are connected by described the first pipeline (201).
3. nuclear plant pressure vessels accident exhaust system according to claim 2, it is characterized in that, described accident exhaust apparatus (2) also comprises the second pipeline (203), on described the second pipeline (203), be provided with at least one the second by-pass valve control (204), described the second pipeline (203) and described the first pipeline (201) are in parallel, and at least one described the first by-pass valve control (202) and at least one described the second by-pass valve control (204) are and are arranged in parallel.
4. nuclear plant pressure vessels accident exhaust system according to claim 3, it is characterized in that, described accident exhaust apparatus (2) also comprises control system (205), described the first by-pass valve control (202) and described the second by-pass valve control (204) are electrically connected to described control system (205) respectively, and described control system (205) is for controlling the unlatching of described the first by-pass valve control (202) and described the second by-pass valve control (204) or closing.
5. nuclear plant pressure vessels accident exhaust system according to claim 4, it is characterized in that, on described the first pipeline (201), be also provided with at least one the first thermometer (206) and/or at least one the first pressure gauge (207), on described the second pipeline (203), be also provided with at least one the second thermometer (208) and/or at least one the second pressure gauge (209); Described the first thermometer (206), described the first pressure gauge (207), described the second thermometer (208) and described the second pressure gauge (209) are connected with described control system (205) respectively.
6. nuclear plant pressure vessels accident exhaust system according to claim 5, it is characterized in that, on described the first pipeline (201), be also provided with at least one the first restrictor (210) and/or described the second pipeline (203) and be also provided with at least one the second restrictor (211).
7. nuclear plant pressure vessels accident exhaust system according to claim 1, it is characterized in that, described pressure vessel (1) top is connected with exhaust line (11), end away from the described exhaust line (11) of described pressure vessel (1) is connected with blind flange (12), and hand valve (13) is also installed on described exhaust line (11).
8. nuclear plant pressure vessels accident exhaust system according to claim 7, is characterized in that, the described exhaust line (11) between described pressure vessel (1) and described hand valve (13) is connected with described accident exhaust apparatus (2).
9. nuclear plant pressure vessels accident exhaust system according to claim 3, is characterized in that, the quantity of described the first by-pass valve control (202) is 2, and the quantity of described the second by-pass valve control (204) is 2; Described the first by-pass valve control (202) is solenoid valve or motorized valve or pneumatic valve, and described the second by-pass valve control (204) is solenoid valve or motorized valve or pneumatic valve.
10. nuclear plant pressure vessels accident exhaust system according to claim 1, is characterized in that, described pressure relief device (3) comprises pressurizer relief tank.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
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| CN201320509541.8U CN203397706U (en) | 2013-08-20 | 2013-08-20 | Nuclear power station pressure vessel accident exhaust system |
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| Application Number | Priority Date | Filing Date | Title |
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| CN201320509541.8U CN203397706U (en) | 2013-08-20 | 2013-08-20 | Nuclear power station pressure vessel accident exhaust system |
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| CN203397706U true CN203397706U (en) | 2014-01-15 |
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| CN201320509541.8U Expired - Lifetime CN203397706U (en) | 2013-08-20 | 2013-08-20 | Nuclear power station pressure vessel accident exhaust system |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN104409112A (en) * | 2014-12-03 | 2015-03-11 | 中国核动力研究设计院 | Containment recycling system |
| CN111755139A (en) * | 2020-04-20 | 2020-10-09 | 中国核电工程有限公司 | Design method of pressure vessel stack top exhaust control strategy under accident condition |
-
2013
- 2013-08-20 CN CN201320509541.8U patent/CN203397706U/en not_active Expired - Lifetime
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN104409112A (en) * | 2014-12-03 | 2015-03-11 | 中国核动力研究设计院 | Containment recycling system |
| CN104409112B (en) * | 2014-12-03 | 2017-07-04 | 中国核动力研究设计院 | Containment recirculating system |
| CN111755139A (en) * | 2020-04-20 | 2020-10-09 | 中国核电工程有限公司 | Design method of pressure vessel stack top exhaust control strategy under accident condition |
| CN111755139B (en) * | 2020-04-20 | 2023-11-14 | 中国核电工程有限公司 | Design method of pressure vessel stack top exhaust control strategy under accident working condition |
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Address after: 518023 No. 69 Shennan Middle Road, Shenzhen, Guangdong, Futian District Co-patentee after: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Co.,Ltd. Patentee after: CHINA NUCLEAR POWER ENGINEERING Co.,Ltd. Co-patentee after: CHINA GENERAL NUCLEAR POWER Corp. Address before: 518023 No. 69 Shennan Middle Road, Shenzhen, Guangdong, Futian District Co-patentee before: China Nuclear Power Technology Research Institute Co.,Ltd. Patentee before: CHINA NUCLEAR POWER ENGINEERING Co.,Ltd. Co-patentee before: CHINA GENERAL NUCLEAR POWER Corp. |
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| CP01 | Change in the name or title of a patent holder | ||
| CX01 | Expiry of patent term |
Granted publication date: 20140115 |
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| CX01 | Expiry of patent term |