CN104217773A - Nuclear power plant steel safe containment vessel heat-conductive device - Google Patents
Nuclear power plant steel safe containment vessel heat-conductive device Download PDFInfo
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- CN104217773A CN104217773A CN201410371100.5A CN201410371100A CN104217773A CN 104217773 A CN104217773 A CN 104217773A CN 201410371100 A CN201410371100 A CN 201410371100A CN 104217773 A CN104217773 A CN 104217773A
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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 invention relates to a nuclear power plant steel safe containment vessel heat-conductive device and belongs to the field of nuclear power plant steel safe containment vessel passive heat conduction. Main solutions in the prior art are divide into active systems and passive systems, wherein the active systems are excessively depended on external power supplies, cannot be used after switch off, are complex in devices and are difficult to maintain and repair; and the passive systems are low in heat exchange power, are long in heat exchange time, and having risks of unavailable natural circulations of the systems and radioactivity leakage caused by penetration on the containment vessel and the like. The nuclear power plant steel safe containment vessel heat-conductive device includes a steel containment vessel. A concrete water tank is disposed outside the steel containment vessel. A water supplying pipeline is connected to the top of the concrete water tank and a steam heat-dissipating device is arranged above the concrete water tank. The steel containment vessel is fixed in the concrete water tank. By means of the device, heat in a nuclear power plant steel safe containment vessel can be dissipated safelier and more efficiently so that a problem of heat dissipation of the safe containment vessel in a nuclear power plant after accident can be completely solved.
Description
Technical field
The invention belongs to the non-active heat conduction field of nuclear power plant's steel containment vessel, be specifically related to a kind of nuclear power plant steel containment vessel heat-transfer device.
Background technology
Design of nuclear power plant considers depth defense principle, and design multibarrier escapes effectively to prevent radiomaterial, to protect the safety of power plant laborer and the public.Containment, as last one barrier, has vital role for containing the radiomaterial revealed.Once cut appears in reactor coolant loop pressure boundary, the radiomaterial of leakage enters in containment.After accident, the temperature and pressure of containment raises rapidly, is the integrality of the shell that ensures safety, and need realize the fast cooling step-down of containment.
As shown in Figure 1, current mainstream solution is divided into active system and passive system, comprises spray system 11, built-in material-changing water tank 12, chemical addition agent case 13, feeding spraying pump 14, spray heat exchanger 15, heat-exchanging water tank 16, steam-water separator 17.Traditional containment decrease temperature and pressure relies on active containment spray system, by electrodynamic pump, the chilled water be arranged in the built-in material-changing water tank of containment inner bottom part is extracted to the containment spray system being arranged in containment top, and in containment, spray chilled water from top to bottom, the response of this means decrease temperature and pressure is fast, effective, but too rely on external power source, after the beyond design basis accidents such as station blackout, containment spray system is unavailable, loses containment decrease temperature and pressure means; And active system equipment and parts more more complicated, maintenance difficulty is large.Three generations's nuclear power technology many employings passive containment thermal conduction system, mainly comprises concrete containment and steel containment vessel two kinds.The non-active heat guiding system of concrete containment utilizes and is arranged in the density difference that the temperature difference between the heat interchanger in containment and the cooling water tank outside containment causes and realizes continuous print Natural Circulation, constantly takes the heat in containment out of.Steel containment vessel heat guiding system utilizes the heat in the heat absorption derivation containment of cooling water flow on box hat surface, and heat-exchanging water tank is positioned at containment top, because Action of Gravity Field is in the flowing of box hat surface after accident.It is on the low side that the non-active heat guiding system of concrete containment compares active containment spray system heat exchange power, and passive system needs the longer time to obtaining maximum heat exchange power again from being heated to bring into operation, and is unfavorable for the containment quick heat removal that accident is early stage.Non-active steel containment vessel heat-conducting system cooling water flow conduits design and gas flow organization difficult design and still can not ensure heat-conducting effect.There is system Natural Circulation and cannot to set up and containment runs through the radioactive release equivalent risk caused in non-active concrete containment heat guiding system, and after there is accident, maloperation causes miscarrying fortune or cannot the risk of bringing normally into operation.
Summary of the invention
For the defect existed in prior art, the object of this invention is to provide a kind of nuclear power plant steel containment vessel heat-transfer device.This device is applicable to steel containment vessel nuclear power plant, safer, more effectively can carry out heat extraction to nuclear power plant's steel containment vessel, thoroughly containment heat removal issue after solution nuclear power plant accident.
For reaching above object, the technical solution used in the present invention is: a kind of nuclear power plant steel containment vessel heat-transfer device, comprise steel containment vessel, concrete basin is outside equipped with at described steel containment vessel, moisturizing pipeline is connected with at concrete basin top, steam heat release is provided with above concrete basin, described steel containment vessel is fixed in concrete basin, inject chilled water by filling pipe alignment concrete basin to transfer the height of water level of whole concrete basin, and the steam produced after discharging chilled water heat absorption by steam discharging device.
Further, the coated anticorrosive heat conducting coating of described steel containment vessel outside surface.
Further, arrange in described concrete basin and stir and make muddy mechanical facility.
Further, the bottom of described concrete basin arranges Level monitor.
Further, the steam discharging device of the top of described concrete basin is set to U-tube.
Further, described chilled water is demineralized water.
Effect of the present invention is: adopt nuclear power plant of the present invention steel containment vessel heat-transfer device, achieve passive containment heat conduction truly, compare active containment spray system, enormously simplify system and circuit design, decrease the quantity of active component, avoid the risk that active component lost efficacy, and simplify the design of system related Control System and back-up system.This design is compared to current passive containment thermal conduction system, and without the need to the system starting process of long period, this containment heat-transfer device ensures zero time of day response after accident, and decreases pipeline thermal resistance, and cold and hot physical contact between media, heat exchange efficiency is higher.The program eliminates valve event, avoids the risk that maloperation or accident late gate fault cause realizing containment heat exchange.For this design without the need to designing malfunction protocol and starting strategy, the predicted operation event that normally runs to can be covered, arrive all operating modes such as design basis accident and beyond design basis accident again.
Accompanying drawing explanation
Fig. 1 is containment heat-conducting system structural representation in prior art;
Fig. 2 is the structural representation of nuclear power plant of the present invention steel containment vessel heat-transfer device;
In Fig. 1: 11 spray systems, 12 built-in material-changing water tanks, 13 chemical addition agent casees, 14 feeding spraying pumps, 15 spray heat exchangers, 16 heat-exchanging water tanks, 17 steam-water separators;
In Fig. 2: 1 concrete basin, 2 steel containment vessels, 3 anticorrosive heat conducting coatings, 4 moisturizing pipelines, 5 stir and make muddy mechanical facility, 6 steam discharging devices, 7 Level monitors, 8 chilled waters.
Embodiment
Below in conjunction with the drawings and specific embodiments, the invention will be further described.
As shown in Figure 2, a kind of nuclear power plant steel containment vessel heat-transfer device, comprise concrete basin 1, be fixed on the steel containment vessel 2 in concrete basin 1, be arranged on the moisturizing pipeline 4 at concrete basin top, and the steam heat release 6 be arranged on above concrete basin 1, inject to concrete basin 1 height of water level that chilled water 8 adjusts concrete basin 1 by the moisturizing pipeline 4 being arranged on concrete basin top, and the steam produced after sending chilled water 8 to absorb heat by the steam discharging device 6 above concrete basin 1.
In the present embodiment, the coated anticorrosive heat conducting coating 3 of described steel containment vessel 2 outside surface.
Arrange in concrete basin 1 and stir and make muddy mechanical facility 5.
The bottom of concrete basin 1 arranges Level monitor 7.
The steam discharging device 6 of the top of concrete basin 1 is set to U-tube.
Described chilled water 8 is demineralized waters.
Can be found out by above-described embodiment, beneficial effect of the present invention is as follows: the accidents such as the heat release in reactor operation process and heat-transfer pipe cut all can make the temperature and pressure of containment inside raise, be immersed in chilled water by all or part of for steel containment vessel, utilize the anticorrosive heat conducting coating of containment outside surface processed, the heat in steel containment vessel is exported in chilled water by box hat.
Surrounding in cooling pond arranges and stirs and make muddy mechanical facility, strengthens the flowing of chilled water on the one hand, improves the convection transfer rate of steel containment vessel outside surface; Secondly, promote the blending of cold fluid and hot fluid, reduce the localized heat stress of steel containment vessel; In addition, the discharge of the steam produced after being beneficial to chilled water heat absorption.
Chilled water adopts demineralized water, to prevent steel containment vessel and concrete basin surface corrosion.And Level monitor is set bottom concrete basin, at concrete basin top, moisturizing pipeline is set, moisturizing signal is triggered after concrete water pool water level is lower than alarming value, be that concrete basin supplements demineralized water by moisturizing pipeline, to ensure the chilled water loading amount that concrete basin remains enough.
U-tube steam discharging device is set above concrete basin, is designed by rational U-tube, make the water vapour normal discharge in concrete basin, and ensure water quality in During Process of Long-term Operation.
Device of the present invention is not limited to the embodiment described in embodiment, and those skilled in the art's technical scheme according to the present invention draws and other embodiment belongs to technological innovation scope of the present invention equally.
Claims (6)
1. nuclear power plant's steel containment vessel heat-transfer device, comprise steel containment vessel (2), it is characterized in that: be outside equipped with concrete basin (1) at described steel containment vessel (2), moisturizing pipeline (4) is connected with at concrete basin (1) top, steam heat release (6) is provided with in concrete basin (1) top, described steel containment vessel (2) is fixed in concrete basin (1), inject chilled water (8) by moisturizing pipeline (4) to concrete basin (1) to transfer the height of water level of whole concrete basin (1), and the steam produced after discharging chilled water (8) heat absorption by steam discharging device (6).
2. a kind of nuclear power plant as claimed in claim 1 steel containment vessel heat-transfer device, is characterized in that: the coated anticorrosive heat conducting coating (3) of described steel containment vessel (2) outside surface.
3. a kind of nuclear power plant as claimed in claim 1 steel containment vessel heat-transfer device, is characterized in that: arrange in described concrete basin (1) and stir and make muddy mechanical facility (5).
4. a kind of nuclear power plant steel containment vessel heat-transfer device as described in claim 1 or 2 or 3, is characterized in that: the bottom of described concrete basin (1) arranges Level monitor (7).
5. a kind of nuclear power plant steel containment vessel heat-transfer device as described in claim 1 or 2 or 3, is characterized in that: the steam discharging device (6) of the top of described concrete basin (1) is set to U-tube.
6. a kind of nuclear power plant steel containment vessel heat-transfer device as described in claim 1 or 2 or 3, is characterized in that: described chilled water (8) is demineralized water.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410371100.5A CN104217773B (en) | 2014-07-30 | A kind of nuclear power plant steel containment vessel heat-transfer device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410371100.5A CN104217773B (en) | 2014-07-30 | A kind of nuclear power plant steel containment vessel heat-transfer device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN104217773A true CN104217773A (en) | 2014-12-17 |
| CN104217773B CN104217773B (en) | 2017-01-04 |
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Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104934078A (en) * | 2015-05-11 | 2015-09-23 | 中国核电工程有限公司 | Passive containment cooling system keeping dynamic circulation of cooling water |
| CN105741888A (en) * | 2016-03-29 | 2016-07-06 | 中国人民解放军92609部队 | Non-kinetic energy containment cooling system for pressurized water reactor |
| CN108682461A (en) * | 2018-05-15 | 2018-10-19 | 中国核电工程有限公司 | A kind of passive air cooling system of containment for small-sized heap |
| CN110783005A (en) * | 2019-10-08 | 2020-02-11 | 中国核电工程有限公司 | Passive heat conduction device and secondary side passive cooling system |
| CN112053792A (en) * | 2020-08-31 | 2020-12-08 | 中国核电工程有限公司 | Nuclear power plant post-accident containment heat exporting system |
| CN112951457A (en) * | 2021-03-05 | 2021-06-11 | 哈尔滨工程大学 | PCS long-term heat exchange water tank with parallel channels |
| CN113593733A (en) * | 2021-07-02 | 2021-11-02 | 中国核电工程有限公司 | Passive steel containment heat exporting system |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20090161812A1 (en) * | 2007-11-15 | 2009-06-25 | The State of OR acting by and through the State System of Higher Education on Behalf of OR State | Evacuated containment vessel for a nuclear reactor |
| CN102194533A (en) * | 2011-05-09 | 2011-09-21 | 中科华核电技术研究院有限公司 | Reactor safety system |
| CN202126850U (en) * | 2011-06-03 | 2012-01-25 | 上海核工程研究设计院 | Impoundment type passive double-layer containment vessel |
| CN202549316U (en) * | 2012-02-29 | 2012-11-21 | 上海核工程研究设计院 | Non-active safe shell cooling system with combination of water logging and air cooling |
| CN103489489A (en) * | 2012-06-13 | 2014-01-01 | 中国核动力研究设计院 | Passive containment spraying-submerged cooling system |
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20090161812A1 (en) * | 2007-11-15 | 2009-06-25 | The State of OR acting by and through the State System of Higher Education on Behalf of OR State | Evacuated containment vessel for a nuclear reactor |
| CN102194533A (en) * | 2011-05-09 | 2011-09-21 | 中科华核电技术研究院有限公司 | Reactor safety system |
| CN202126850U (en) * | 2011-06-03 | 2012-01-25 | 上海核工程研究设计院 | Impoundment type passive double-layer containment vessel |
| CN202549316U (en) * | 2012-02-29 | 2012-11-21 | 上海核工程研究设计院 | Non-active safe shell cooling system with combination of water logging and air cooling |
| CN103489489A (en) * | 2012-06-13 | 2014-01-01 | 中国核动力研究设计院 | Passive containment spraying-submerged cooling system |
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104934078A (en) * | 2015-05-11 | 2015-09-23 | 中国核电工程有限公司 | Passive containment cooling system keeping dynamic circulation of cooling water |
| CN105741888A (en) * | 2016-03-29 | 2016-07-06 | 中国人民解放军92609部队 | Non-kinetic energy containment cooling system for pressurized water reactor |
| CN108682461A (en) * | 2018-05-15 | 2018-10-19 | 中国核电工程有限公司 | A kind of passive air cooling system of containment for small-sized heap |
| CN108682461B (en) * | 2018-05-15 | 2023-08-15 | 中国核电工程有限公司 | Containment passive air cooling system for small stacks |
| CN110783005A (en) * | 2019-10-08 | 2020-02-11 | 中国核电工程有限公司 | Passive heat conduction device and secondary side passive cooling system |
| CN110783005B (en) * | 2019-10-08 | 2021-10-01 | 中国核电工程有限公司 | Passive heat conduction device and secondary side passive cooling system |
| CN112053792A (en) * | 2020-08-31 | 2020-12-08 | 中国核电工程有限公司 | Nuclear power plant post-accident containment heat exporting system |
| CN112053792B (en) * | 2020-08-31 | 2023-02-17 | 中国核电工程有限公司 | Nuclear power plant post-accident containment heat exporting system |
| CN112951457A (en) * | 2021-03-05 | 2021-06-11 | 哈尔滨工程大学 | PCS long-term heat exchange water tank with parallel channels |
| CN113593733A (en) * | 2021-07-02 | 2021-11-02 | 中国核电工程有限公司 | Passive steel containment heat exporting system |
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