CN203607101U - Ventilating-exhausting system of nuclear power containment vessel - Google Patents
Ventilating-exhausting system of nuclear power containment vessel Download PDFInfo
- Publication number
- CN203607101U CN203607101U CN201320663799.3U CN201320663799U CN203607101U CN 203607101 U CN203607101 U CN 203607101U CN 201320663799 U CN201320663799 U CN 201320663799U CN 203607101 U CN203607101 U CN 203607101U
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- Prior art keywords
- containment
- containment vessel
- air filtering
- isolating valve
- filtering system
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- 230000035515 penetration Effects 0.000 claims abstract description 46
- 238000001914 filtration Methods 0.000 claims description 46
- 238000002955 isolation Methods 0.000 claims description 45
- 238000012544 monitoring process Methods 0.000 claims description 8
- 230000005855 radiation Effects 0.000 claims description 6
- 238000004140 cleaning Methods 0.000 claims description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 7
- 230000002285 radioactive effect Effects 0.000 abstract description 2
- 239000000443 aerosol Substances 0.000 abstract 1
- 230000000717 retained effect Effects 0.000 abstract 1
- 230000037361 pathway Effects 0.000 description 11
- 238000005516 engineering process Methods 0.000 description 4
- 239000007789 gas Substances 0.000 description 4
- 230000009286 beneficial effect Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000014759 maintenance of location Effects 0.000 description 2
- 238000012502 risk assessment Methods 0.000 description 2
- 230000004888 barrier function Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000007599 discharging Methods 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
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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 relates to a ventilating-exhausting system of a nuclear power containment vessel of a passive pressurized water reactor, and belongs to the technical field of nuclear power. The ventilating-exhausting system structurally comprises two parallel containment vessel isolating valve sets, a containment vessel blowing-in penetration component, an inner connecting pipe of a containment vessel penetration component, and an outer connecting pipe of the containment vessel penetration component, wherein the containment vessel blowing-in penetration component penetrates a containment vessel of a nuclear power plant; the inner connecting pipe and the outer connecting pipe are respectively connected with two ends of the containment vessel blowing-in penetration component; one parallel containment vessel isolating valve set is connected with the other end of the inner connecting pipe in the containment vessel, and the other parallel containment vessel isolating valve set is connected with the other end of the outer connecting pipe outside the containment vessel; the containment vessel isolating valve set outside the containment vessel is connected with a chimney connecting pipe of the power plant through a containment vessel exhausting purifying device. According to the ventilating-exhausting system of the nuclear power containment vessel, the isolating valve sets provide a controllable containment vessel exhausting path for the passive pressurized water reactor in case of serious accidents, and thus the problem that radioactive aerosol is retained during pressure releasing and exhausting of the containment vessel can be solved.
Description
Technical field
The utility model relates to a kind of ventilating system, especially relates to a kind of ventilating system of non-active compressed water reactor nuclear power containment, belongs to nuclear power technology field.
Background technology
Along with the development of nuclear power technology and the utilization of nuclear power, each state all recognizes can not get rid of the possibility that nuclear safety accident occurs completely.Have an accident or when fault, npp safety shell is to prevent that radioactive product is discharged into last one barrier in environment in nuclear power plant.For example, in the time that the major accident that reactor core burn through pressure vessel occurs occurs, the incondensable gas causing due to reaction constantly increases, and causes the pressure in containment constantly to raise, and finally may destroy the integrality of containment, causes radiomaterial outwards to discharge.Therefore, in Construction of Nuclear Electricity, must consider alleviation and counter-measure when major accident occurs.
Containment exhaust, as a part important in Severe accident management, is one of countermeasure of Severe accident management.But not the containment exhaust of active presurized water reactor AP1000 is considered to an impossible alleviation action, therefore at AP1000PRA(Probabilistic Risk Assessment, probabilistic risk assessment) analyze in do not do consider.But, in order to meet U.S. NRC(Nuclear Regulatory Commission, NRC) management expectancy to containment performance, really, the analytical proof of coming to a conclusion, boost in event at the containment that can not alleviate, can prevent that radiomaterial from controllably not discharging to environment by effective containment exhaust.
Under the operating mode of normal operation, the pressure of AP1000 npp safety shell is that VFS controls by containment air filtering system (Containment Air Filtration System), but VFS system is non-security related system, under the operating mode of major accident, can not use.Under the operating mode of AP1000 nuclear power plant major accident, containment is isolated, containment internal pressure constantly rises due to the increase of various gas flows, for the pressure that guarantees containment is no more than maximum design pressure, can take multinomial unloading pressure means including containment exhaust to guarantee the integrality of containment, avoid the not controllably discharge of a large amount of radiomaterials.But for the exhaust release mode of containment, AP1000 nuclear power plant does not consider corresponding system design scheme in the time of design.
Summary of the invention
In view of the foregoing, the utility model provides a kind of vented exhaust system of Nuclear Safety shell, can under major accident operating mode, containment faces superpressure risk time, opens for containment release, has effectively solved the release exhausting problem of containment.
For solving the problems of the technologies described above, the technical solution of the utility model is achieved in that a kind of vented exhaust system of Nuclear Safety shell, comprise the containment isolating valve group of two groups of parallel connections, through the containment air-supply penetration piece of npp safety shell, the containment penetration shell inner connecting tube and the containment penetration shell extension tube attached that are connected with the two ends of containment air-supply penetration piece, wherein one group of parallel containment isolating valve group is connected with the other end of the containment penetration inner connecting tube in containment inside, another is organized parallel safety isolating valve group and is connected with the other end of the containment penetration extension tube attached in containment outside, containment isolating valve group outside described containment is taken over and is connected with chimney of electric plant by containment emission-control equipment.
Further, described each parallel containment isolating valve group is made up of two parallel containment isolating valves.
Further, wherein the each containment isolating valve in the containment isolating valve group of containment inside is all first connected in series with exhaust screen.
Further, wherein between the containment isolating valve group of containment outside and containment emission-control equipment, be connected to an isolation valve.
Further, described containment emission-control equipment and chimney of electric plant are serially connected with rupture disk, throttling orifice plate and radiation monitoring equipment between taking over successively.
Further, on the module of described rupture disk and throttling orifice plate composition and be connected to stop valve, described stop valve is opened in the time that needs maintain containment emission-control equipment.
Further, one end of described containment air-supply penetration piece is connected with one end of one first containment air filtering system isolation valve with described containment penetration shell inner connecting tube, the other end of described containment air-supply penetration piece is connected with one end of one second containment air filtering system isolation valve with containment penetration shell extension tube attached, described the first containment air filtering system isolation valve and described the second containment air filtering system isolation valve nuclear power plant under major accident operating mode in closed condition.
Further, the other end of described the first containment air filtering system isolation valve and described the second containment air filtering system isolation valve is connected with containment air filtering system, described the first containment air filtering system isolation valve and described the second containment air filtering system isolation valve in the time that containment air filtering system participates in the cleaning action of containment in opening.
Further, described the first containment air filtering system isolation valve is positioned at containment inside, and described the second containment air filtering system isolation valve is positioned at containment outside.
The beneficial effects of the utility model are: the utility model is non-active presurized water reactor by safety isolating valve group, be that AP1000 nuclear power plant provides controlled containment exhaust pathway under major accident operating mode, radioaerosol retention problems while efficiently solving containment release exhaust.
In addition, under major accident operating mode, for AP1000 containment provides a kind of release mode, guarantee the integrality of containment, avoided containment to lose efficacy and cause a large amount of radiomaterials controllably not discharge; Can reduce the radioactivity of containment exhaust, thereby improve the security of AP1000 nuclear power plant simultaneously.
Above-mentioned explanation is only the general introduction of technical solutions of the utility model, in order to better understand technological means of the present utility model, and can be implemented according to the content of instructions, and for above-mentioned purpose of the present utility model, feature and advantage can be become apparent, below especially exemplified by preferred embodiment, and coordinate accompanying drawing, be described in detail as follows.
Accompanying drawing explanation
Fig. 1 is the vented exhaust system architecture schematic diagram of the utility model Nuclear Safety shell.
Symbol description in figure: the 1-the first exhaust screen, the 2-the second exhaust screen, the 3-the first containment isolating valve, the 4-the second containment isolating valve, 5-containment penetration shell inner connecting tube, 6-containment penetration shell extension tube attached, the 7-the three containment isolating valve, the 8-the four containment isolating valve, 9-isolation valve, 10-containment emission-control equipment, 11-rupture disk, 12-throttling orifice plate, 13-stop valve, 14-radiation monitoring equipment, 15-chimney of electric plant is taken over, 16-containment air-supply penetration piece, the 17-the first containment air filtering system isolation valve, the 18-the second containment air filtering system isolation valve.
Embodiment:
Technological means and effect of taking for reaching predetermined object for further setting forth the utility model, below in conjunction with accompanying drawing and preferred embodiment, to embodiment, structure, feature and the effect thereof of the vented exhaust system according to the Nuclear Safety shell the utility model proposes, be described in detail as follows.
As shown in Figure 1, the utility model provides a kind of vented exhaust system of non-active compressed water reactor nuclear power containment, it comprises the first exhaust screen 1, the second exhaust screen 2, the first containment isolating valve 3, the second containment isolating valve 4, containment penetration shell inner connecting tube 5, containment penetration shell extension tube attached 6, the 3rd containment isolating valve 7, the 4th containment isolating valve 8, isolation valve 9, containment filtration containment emission-control equipment 10, rupture disk 11, throttling orifice plate 12, stop valve 13, radiation monitoring equipment 14, chimney of electric plant takes over 15, containment air-supply penetration piece 16, the first containment air filtering system (Containment Air Filtration System, VFS) isolation valve 17 and the second containment air filtering system isolation valve 18.
Described containment air-supply penetration piece 16 runs through Nuclear Safety shell, its two ends lay respectively at containment inside and containment outside, its first end that is positioned at containment inside is connected with the first end of containment penetration inner connecting tube 5, and its second end that is positioned at containment outside is connected with the first end of containment penetration extension tube attached 6.
Described the first containment air filtering system isolation valve 17 is positioned at containment inside, and its one end is connected with the first end of containment air-supply penetration piece 16 with the first end of containment penetration inner connecting tube 5, and the other end is connected with containment air filtering system; The second containment air filtering system isolation valve 18 is positioned at containment outside, and its one end is connected with the second end of containment air-supply penetration piece 16 with the first end of containment penetration extension tube attached 6, and the other end is connected with containment air filtering system.In the present embodiment, the first containment air filtering system isolation valve 17 and the second containment air filtering system isolation valve 18 are pneumatic isolation valve.
Described the first containment isolating valve 3 and the second containment isolating valve 4 parallel connections and be all positioned at containment inside, the first containment isolating valve 3 and the first parallel containment isolating valve group of the second containment isolating valve 4 composition, the first containment isolating valve group is connected with the second end of containment penetration inner connecting tube 5, before the first containment isolating valve 3, be serially connected with the first exhaust screen 1, before the second containment isolating valve 4, be serially connected with the second exhaust screen 2.
Described the 3rd containment isolating valve 7 and the 4th containment isolating valve 8 parallel connections and be all positioned at containment outside, the 3rd containment isolating valve 7 and the second parallel containment isolating valve group of the 4th containment isolating valve 8 composition, the second end of described containment penetration extension tube attached 6 is connected with the second containment isolating valve group.In the present embodiment, the first containment isolating valve 3, the second containment isolating valve 4, the 3rd containment isolating valve 7 and the 4th containment isolating valve 8 are electronic isolation valve, and under normal circumstances in closed condition.
The second containment isolating valve group of described containment outside is connected with containment emission-control equipment 10 by isolation valve 9, and in the present embodiment, described isolation valve 9 is manual isolation valve, and under normal circumstances in open mode.Described containment emission-control equipment 10 is serially connected with rupture disk 11, throttling orifice plate 12, radiation monitoring equipment 14 successively along discharge directions, then takes over and 15 is connected with chimney of electric plant, on the module forming at rupture disk 11 and throttling orifice plate 12 and be connected to stop valve 13.When system of the present utility model is in stand-by state; and need to maintain containment emission-control equipment 10 time; can open stop valve 13, the interface carrying by containment emission-control equipment 10 is filled with blanket gas, and closes stop valve 13 in the time that inflation finishes.
Can be known by narration above, in containment vented exhaust system of the present utility model, the first exhaust screen 1, the first containment isolating valve 3, containment penetration shell inner connecting tube 5, containment air-supply penetration piece 16, containment penetration shell extension tube attached 7, the 3rd containment isolating valve 7, isolation valve 9, containment emission-control equipment 10, rupture disk 11, throttling orifice plate 12 and chimney of electric plant are taken over 15 composition the first exhaust pathways.
The second exhaust screen 2, the second containment isolating valve 4, containment penetration shell inner connecting tube 5, containment air-supply penetration piece 16, containment penetration shell extension tube attached 7, the 4th containment isolating valve 8, isolation valve 9, containment emission-control equipment 10, rupture disk 11, throttling orifice plate 12 and chimney of electric plant are taken over 15 composition the second exhaust pathways.Radiation monitoring equipment 14 is positioned on the first exhaust pathway and the second exhaust pathway.
Operating mode in AP1000 nuclear power plant in normal operation, and containment air filtering system need to participate in the cleaning action of containment, need to open the first containment air filtering system isolation valve 17 and the second containment air filtering system isolation valve 18, make containment air filtering system can participate in the cleaning of containment; In the time not needing containment to clean, can close the first containment air filtering system isolation valve 17 and the second containment air filtering system isolation valve 18.
Under operating mode in AP1000 nuclear power plant in major accident, the first containment air filtering system isolation valve 17 and the second containment air filtering system isolation valve 18 are in closed condition.In the time that containment generation superpressure is dangerous, open the first containment isolating valve 3 and the 3rd containment isolating valve 7 by master-control room operator remote manual.If the first containment isolating valve 3 or the 3rd containment isolating valve 7 are opened failure, the first exhaust pathway lost efficacy, remote manual is closed the first containment isolating valve 3 and/or the 3rd containment isolating valve 7 that send OPEN, and remote manual opens the second containment isolating valve 4 and the 4th containment isolating valve 8, carry out exhaust by the second exhaust pathway; In the situation that allowing, also can open first to fourth containment isolating valve simultaneously, utilize the first exhaust pathway and the second exhaust pathway to carry out exhaust simultaneously, and the radioactivity of final emission gases is monitored by radiation monitoring equipment 14 at the end of exhaust pathway, monitoring result shows and record at master-control room.
The beneficial effects of the utility model are: the utility model is non-active presurized water reactor by safety isolating valve group, be that AP1000 nuclear power plant provides controlled containment exhaust pathway under major accident operating mode, radioaerosol retention problems while efficiently solving containment release exhaust.
In addition, under major accident operating mode, for AP1000 containment provides a kind of release mode, guarantee the integrality of containment, avoided containment to lose efficacy and cause a large amount of radiomaterials controllably not discharge; Can reduce the radioactivity of containment exhaust, thereby improve the security of AP1000 nuclear power plant simultaneously.
The above, it is only the detailed description that realizes the utility model specific embodiment of the utility model instructions description and graphic, for illustration and unrestricted, but feature of the present utility model is not limited to this, those skilled in the art obviously understand, all scopes of the present utility model should be as the criterion with the protection domain of its claim, do not deviating under the prerequisite of invention spirit that appended claims defines and invention scope, all other embodiment that variation similar with it implemented according to spirit of the present utility model, all should be included among protection category of the present utility model.
Claims (9)
1. the vented exhaust system of a Nuclear Safety shell, comprise the containment air-supply penetration piece that runs through containment, the containment penetration shell inner connecting tube and the containment penetration shell extension tube attached that are connected with the two ends of containment air-supply penetration piece, it is characterized in that: the vented exhaust system of described Nuclear Safety shell also comprises two groups of parallel containment isolating valve groups, wherein one group of parallel containment isolating valve group is connected with the other end of the containment penetration inner connecting tube in containment inside, another is organized parallel safety isolating valve group and is connected with the other end of the containment penetration extension tube attached in containment outside, containment isolating valve group outside described containment is taken over and is connected with chimney of electric plant by containment emission-control equipment.
2. the vented exhaust system of Nuclear Safety shell according to claim 1, is characterized in that: described each parallel containment isolating valve group is made up of two parallel containment isolating valves.
3. the vented exhaust system of Nuclear Safety shell according to claim 2, is characterized in that: wherein the each containment isolating valve in the containment isolating valve group of containment inside is all first connected in series with exhaust screen.
4. the vented exhaust system of Nuclear Safety shell according to claim 2, is characterized in that: wherein between the containment isolating valve group of containment outside and containment emission-control equipment, be connected to an isolation valve.
5. the vented exhaust system of Nuclear Safety shell according to claim 1, is characterized in that: described containment emission-control equipment and chimney of electric plant are serially connected with rupture disk, throttling orifice plate and radiation monitoring equipment between taking over successively.
6. the vented exhaust system of Nuclear Safety shell according to claim 5, is characterized in that: on the module of described rupture disk and throttling orifice plate composition and be connected to stop valve, described stop valve is opened in the time that needs maintain containment emission-control equipment.
7. the vented exhaust system of Nuclear Safety shell according to claim 1, it is characterized in that: one end of described containment air-supply penetration piece is connected with one end of one first containment air filtering system isolation valve with described containment penetration shell inner connecting tube, the other end of described containment air-supply penetration piece is connected with one end of one second containment air filtering system isolation valve with containment penetration shell extension tube attached, described the first containment air filtering system isolation valve and described the second containment air filtering system isolation valve nuclear power plant under major accident operating mode in closed condition.
8. the vented exhaust system of Nuclear Safety shell according to claim 7, it is characterized in that: the other end of described the first containment air filtering system isolation valve and described the second containment air filtering system isolation valve is connected with containment air filtering system, described the first containment air filtering system isolation valve and described the second containment air filtering system isolation valve in the time that containment air filtering system participates in the cleaning action of containment in opening.
9. according to the vented exhaust system of the Nuclear Safety shell described in claim 7 or 8, it is characterized in that: described the first containment air filtering system isolation valve is positioned at containment inside, described the second containment air filtering system isolation valve is positioned at containment outside.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201320663799.3U CN203607101U (en) | 2013-10-25 | 2013-10-25 | Ventilating-exhausting system of nuclear power containment vessel |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201320663799.3U CN203607101U (en) | 2013-10-25 | 2013-10-25 | Ventilating-exhausting system of nuclear power containment vessel |
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| CN203607101U true CN203607101U (en) | 2014-05-21 |
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| CN201320663799.3U Expired - Lifetime CN203607101U (en) | 2013-10-25 | 2013-10-25 | Ventilating-exhausting system of nuclear power containment vessel |
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104517658A (en) * | 2014-12-24 | 2015-04-15 | 长江勘测规划设计研究有限责任公司 | Airborne radioactivity diffusion prevention method for underground nuclear power plant |
| CN104595999A (en) * | 2014-12-03 | 2015-05-06 | 中国核电工程有限公司 | Nuclear power station master-control room passive driven indoor air cooling and purifying system |
| CN108154945A (en) * | 2016-12-06 | 2018-06-12 | 中广核研究院有限公司 | A kind of system that containment gas filtration discharge is realized under major accident operating mode |
| CN109405160A (en) * | 2018-09-18 | 2019-03-01 | 中广核研究院有限公司 | A kind of Containment for PWR Nuclear Power Plant ventilating system |
| CN112037948A (en) * | 2020-09-08 | 2020-12-04 | 三门核电有限公司 | AP1000 containment overall leakage rate test pressure relief system and method |
-
2013
- 2013-10-25 CN CN201320663799.3U patent/CN203607101U/en not_active Expired - Lifetime
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104595999A (en) * | 2014-12-03 | 2015-05-06 | 中国核电工程有限公司 | Nuclear power station master-control room passive driven indoor air cooling and purifying system |
| CN104595999B (en) * | 2014-12-03 | 2017-08-25 | 中国核电工程有限公司 | The passive room air cooling of master control room of nuclear power station and cleaning system |
| CN104517658A (en) * | 2014-12-24 | 2015-04-15 | 长江勘测规划设计研究有限责任公司 | Airborne radioactivity diffusion prevention method for underground nuclear power plant |
| CN108154945A (en) * | 2016-12-06 | 2018-06-12 | 中广核研究院有限公司 | A kind of system that containment gas filtration discharge is realized under major accident operating mode |
| CN109405160A (en) * | 2018-09-18 | 2019-03-01 | 中广核研究院有限公司 | A kind of Containment for PWR Nuclear Power Plant ventilating system |
| CN112037948A (en) * | 2020-09-08 | 2020-12-04 | 三门核电有限公司 | AP1000 containment overall leakage rate test pressure relief system and method |
| CN112037948B (en) * | 2020-09-08 | 2022-03-18 | 三门核电有限公司 | AP1000 containment overall leakage rate test pressure relief system and method |
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Granted publication date: 20140521 |
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| CX01 | Expiry of patent term |