CN113593733A - Passive steel containment heat exporting system - Google Patents
Passive steel containment heat exporting system Download PDFInfo
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- CN113593733A CN113593733A CN202110752630.4A CN202110752630A CN113593733A CN 113593733 A CN113593733 A CN 113593733A CN 202110752630 A CN202110752630 A CN 202110752630A CN 113593733 A CN113593733 A CN 113593733A
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- cooling water
- cooling
- containment vessel
- containment
- annular cavity
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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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 invention belongs to the technical field of nuclear power plant reactor safety systems, and particularly relates to a passive steel containment vessel heat exporting system, wherein a cooling cover (7) of a closed annular cavity (5) is formed by the side wall of a containment vessel (1) of a reactor and the containment vessel (1), a cooling water loop is arranged on the cooling cover (7), when the containment vessel (1) needs to be cooled, the cooling water loop can inject cooling water into the annular cavity (5) from the bottom of the cooling cover (7) in a passive mode, and the cooling water after heat absorption in the annular cavity (5) can flow back to the cooling water loop from the top of the cooling cover (7) in a passive mode; the containment vessel (1) is made of stainless steel. The invention eliminates the dependence of the traditional active safety system on a safety-level power supply, has higher natural circulation capability and heat removal capability, and provides the capability of relieving the accident consequence for a long time without intervention after the accident.
Description
Technical Field
The invention belongs to the technical field of nuclear power plant reactor safety systems, and particularly relates to a passive steel containment vessel heat exporting system.
Background
The containment is the last containment barrier in a light water reactor nuclear power plant to prevent the release of significant amounts of radioactive fission products from the core to the outside environment. A large amount of high temperature fluids (water and steam) may be released from the reactor cooling circuit into the containment space during nuclear power plant accident conditions, causing significant increases in temperature and pressure, thereby threatening the integrity of the containment structure.
The traditional pressurized water reactor nuclear power plant adopts an active containment spraying system to reduce the pressure and the temperature of a containment, but the method cannot cope with the over-design reference working condition of losing a power supply. Therefore, from the eighties of the last century, passive safety technologies have been studied in the united states, france, germany, russia, and other countries. For example, in a passive containment cooling system (see fig. 1) of the american AP1000, after a signal that the containment pressure is high is generated under an accident condition, a pipe valve connected to a water tank 2 disposed at the top of the containment is opened, and cooling water in the water tank flows out by gravity and covers the outer wall surface of the steel containment to form a liquid film, thereby cooling the containment. On the other hand, air enters from the top inlet 1, flows through the descending channel under the action of the natural circulation driving pressure, returns back and flows upwards to flow over the surface of the liquid film, evaporation of the liquid film is promoted, and heat is further introduced into a final heat trap, namely an atmospheric environment. Also for example
ZL201110437864.6 discloses a passive containment heat removal system based on a natural circulation loop design (see fig. 2). The steam condenses and heats the heat exchanger 3 located in the containment vessel under accident conditions; the fluid in the pipeline loop forms natural circulation flow under the action of the temperature difference of cold and heat sources, and further transfers heat into the cooling water tank 2 above; the water in the cooling water tank 2 is heated and then finally the heat is introduced into the atmosphere through evaporation and boiling. In addition, regarding the steel containment, ZL201410371100.5 discloses a solution based on an external concrete pool for containment, which submerges the containment by injecting cooling water into the external concrete pool, and derives heat from the surface of the steel containment through evaporation phase change of the cooling water in the external concrete pool.
The existing passive containment cooling system is designed by means of natural driving forces such as gravity, density difference and the like, can effectively cope with the limit accident condition of power loss, simplifies the system, reduces the dependence on the intervention of movable equipment and operators, and thus can effectively improve the inherent safety and the economical efficiency of a power station. On the other hand, the current passive system has certain limitations due to the inherent properties of the system design and the passive physical mechanism. For example, in the AP1000 solution, the cooling water directly flows to the environment after flowing through the containment outer wall surface, and the containment cannot be cooled any more. And considering the capacity limit of the top water tank 2, the passive containment cooling system can only be kept effective for 72 hours. In a passive containment heat removal system such as that disclosed in ZL201110437864.6, on one hand, the heat exchanger 3 is located in the containment, and the local accumulation of non-condensable gas near the heat exchanger 3 can weaken the steam condensation heat exchange capacity; on the other hand, due to the limitation of the arrangement space, the contact area of the heat exchanger 3 is limited, so that the further improvement of the heat exchange power is influenced; furthermore, the cooling water tank 2 arranged outside the containment increases the number of penetrations, and the heat exchanger 3 arranged inside the containment introduces an additional risk of containment flooding when broken. The scheme of ZL201410371100.5 discloses aiming at an external concrete pool of a steel containment, in order to realize the submergence of the containment, a concrete pool structure needs to be constructed outside the containment, and the construction difficulty and the cost are high for a large pressurized water reactor power plant with a high containment height (about 60 m); and because the water in the pool can not flow, the heat stratification phenomenon is easy to form, and the whole heat exchange cooling efficiency is reduced.
Disclosure of Invention
The invention aims to provide a passive containment heat exporting system for a light water reactor nuclear power station adopting a steel containment. When the system is in the accident condition (including design benchmark accidents and serious accidents) that the temperature and the pressure in the containment vessel of the nuclear power station are raised and increased, the heat of the containment vessel is quickly and effectively led out by means of a huge heat exchange surface and a natural circulation loop system which are provided by the wall surface of the steel containment vessel, the pressure and the temperature are reduced to lower levels, and acceptable levels are maintained in a long-term stage, so that the integrity of the containment vessel is kept.
In order to achieve the above purpose, the technical scheme adopted by the invention is a passive steel containment vessel heat exporting system, wherein a cooling cover which is arranged on the side wall of a containment vessel of a reactor and forms a closed annular cavity together with the containment vessel is provided with a cooling water loop, when the containment vessel needs to be cooled, the cooling water loop can inject cooling water into the annular cavity from the bottom of the cooling cover in a passive mode, and the cooling water which absorbs heat in the annular cavity can flow back into the cooling water loop from the top of the cooling cover in a passive mode; the containment is made of stainless steel.
Further, the cooling water circuit includes a cooling water tank, and a descent line and an ascent line; the cooling water tank is positioned outside the containment vessel; one end of the descending pipeline is communicated with the bottom of the cooling water tank, and the other end of the descending pipeline is communicated with the side face of the bottom of the cooling cover; one end of the ascending pipeline is communicated with the bottom of the cooling water tank, and the other end of the ascending pipeline is communicated with the side face of the top of the cooling cover.
Further, the cooling water tank is positioned higher than the top of the annular cavity.
Further, the top of the cooling water tank is communicated with the external atmosphere.
Further, the diameters of the ascending pipeline and the descending pipeline are different.
Furthermore, a control valve is arranged on the descending pipeline and can be opened according to a containment pressure signal or an opening instruction of an operator, so that the cooling water flows through the descending pipeline, the annular cavity and the ascending pipeline from the cooling water tank in sequence and finally returns to the cooling water tank.
Furthermore, the cooling water loops are uniformly arranged on the cooling cover.
Further, in the present invention,
the cooling water loop can inject cooling water into the annular cavity from the bottom of the cooling cover by means of gravity;
the cooling water after absorbing heat in the annular cavity can flow back to the cooling water loop from the top of the cooling cover by means of a gravity head formed by fluid density difference.
The invention has the beneficial effects that:
1. the heat in the containment 1 is led out by means of a passive means under the accident condition, the dependence of the traditional active safety system on a safety-level power supply is eliminated, the system and equipment are simplified, and the inherent safety and the economical efficiency of the nuclear power plant are improved.
2. Through the heat exchange between the annular cavity 5 and the outer wall surface of the steel containment, the resistance of heat exchange can be obviously reduced by means of the characteristics that the area of the annular cavity 5 is large and the influence of non-condensable gas is avoided, so that the condensation heat transfer efficiency of the passive heat conduction system is improved.
3. By means of the annular cavity 5 as a heat exchanger and the cooling water tank 2 with a high arrangement height, a high cold and heat source height difference is obtained, so that the system can have high natural circulation capacity and heat discharge capacity.
4. The cooling water stored in the cooling water tank 2 outside the containment vessel 1 can be fully and efficiently utilized, the effective cooling time of the system is prolonged, and the capability of relieving accident consequences for a long time without intervention after an accident is provided.
5. The number of penetrations in the containment vessel 1 may be reduced, thereby improving the sealability of the containment vessel 1.
6. The whole circulating cooling loop is uniformly distributed outside the containment vessel 1, so that the additional risk of flooding the containment vessel 1 when the pipeline is accidentally damaged is eliminated.
Drawings
FIG. 1 is a schematic diagram of a passive containment cooling system for a United states AP1000 according to the background of the invention;
FIG. 2 is a schematic diagram of a passive containment heat removal system based on a natural circulation loop design according to the background of the invention;
FIG. 3 is a schematic diagram of a passive steel containment heat removal system (side view showing a cooling water loop) according to an embodiment of the present invention;
FIG. 4 is a schematic diagram of a passive steel containment heat removal system according to an embodiment of the present invention (top view showing three cooling water circuits);
in the figure: 1-containment vessel, 2-cooling water tank, 3-descending pipeline, 4-control valve, 5-annular cavity, 6-ascending pipeline, 7-cooling cover, 8-top inlet, 9-heat exchanger and 10-reactor pressure vessel.
Detailed Description
The invention is further described below with reference to the figures and examples.
As shown in fig. 3 and 4, the passive steel containment heat exporting system provided by the invention comprises a cooling cover 7 which is arranged on the side wall of a containment 1 of a reactor and forms a closed annular cavity 5 together with the containment 1, wherein a cooling water loop is arranged on the cooling cover 7, when the containment 1 needs to be cooled, the cooling water loop can inject cooling water into the annular cavity 5 from the bottom of the cooling cover 7 in a passive manner (depending on gravity), and the cooling water after absorbing heat in the annular cavity 5 can flow back to the cooling water loop from the top of the cooling cover 7 in a passive manner (depending on a gravity head formed by fluid density difference); the containment vessel 1 is made of stainless steel.
The annular cavity 5 is wrapped on the whole vertical outer wall surface part of the containment vessel 1 and is used for cooling gas in the containment vessel 1 through heat exchange between cooling water and the steel outer wall surface of the containment vessel 1.
The ice water loop comprises a cooling water tank 2, a descending pipeline 3 and an ascending pipeline 6; the cooling water tank 2 is positioned outside the containment vessel 1; one end of the descending pipeline 3 is communicated with the bottom of the cooling water tank 2, and the other end of the descending pipeline is communicated with the side surface of the bottom of the cooling cover 7; one end of the ascending pipeline 6 is communicated with the bottom of the cooling water tank 2, and the other end is communicated with the top side surface of the cooling cover 7.
The cooling water tank 2 is positioned above the top of the annular cavity 5 for providing sufficient natural circulation driving pressure head.
The top of the cooling water tank 2 communicates with the outside atmosphere.
The riser pipe 6 and the downer pipe 3 have different diameters.
The descending pipeline 3 is provided with a control valve 4, the control valve 4 is in a closed state during the normal operation of the nuclear power plant, and can be opened according to a containment pressure signal (when the pressure is higher than a set value of the containment pressure) or according to an opening instruction of an operator under an accident condition (after the control valve 4 is opened, the passive steel containment heat exporting system of the invention is started), so that cooling water flows through the descending pipeline 3, the annular cavity 5 and the ascending pipeline 6 from the cooling water tank 2 in sequence and finally returns to the cooling water tank 2.
The cooling water loops are a plurality of loops and are uniformly arranged on the cooling cover 7.
The practical application of the invention is as follows:
when a breach accident occurs in the primary or secondary circuit of the nuclear power plant reactor coolant, a large amount of high-temperature fluid (water and steam) is released into the inner space of the containment vessel 1, causing a rapid rise in temperature and pressure inside the containment vessel 1. At this time, the control valves 4 of the three cooling water circuits (assuming that there are three cooling water circuits) of the passive steel containment heat export system provided by the present invention are opened simultaneously after receiving a containment pressure signal (specifically, a "containment pressure high signal") or an operator opening command, so that the system starts to be put into operation. The water vapor released from the reactor coolant circuit into the containment vessel 1 is first condensed on the inside surface of the steel containment vessel wall surface and then transferred to the outside surface by a heat transfer mechanism. After the control valve 4 is opened, the cooling water stored in the cooling water tank 2 enters the annular cavity 5 through the descending pipeline 3 under the action of gravity and flows upwards, is heated by absorbing the heat on the outer surface of the steel safety shell wall, establishes natural circulation flow under the action of a driving pressure head generated by density difference, and returns to the cooling water tank 2 through the ascending pipeline 6. After the cooling water in the cooling water tank 2 is heated, heat is conducted into a final heat sink, namely an atmospheric environment, through an evaporation and boiling mechanism. After the system is put into operation, the cooling water capacity in the cooling water tank 2 can ensure that the system maintains effective heat extraction time of over 144 hours, and measures for supplementing cooling water to the cooling water tank 2 need to be considered after 144 hours.
The device according to the present invention is not limited to the embodiments described in the specific embodiments, and those skilled in the art can derive other embodiments according to the technical solutions of the present invention, and also belong to the technical innovation scope of the present invention.
Claims (8)
1. A passive steel containment heat exporting system is characterized in that: the cooling cover (7) is arranged on the side wall of a containment (1) of a reactor and forms a closed annular cavity (5) together with the containment (1), a cooling water loop is arranged on the cooling cover (7), when the containment (1) needs to be cooled, the cooling water loop can inject cooling water into the annular cavity (5) from the bottom of the cooling cover (7) in a passive mode, and the cooling water after absorbing heat in the annular cavity (5) can flow back to the cooling water loop from the top of the cooling cover (7) in the passive mode; the containment (1) is made of stainless steel.
2. The passive steel containment vessel heat removal system of claim 1, wherein: the ice cooling water loop comprises a cooling water tank (2), a descending pipeline (3) and an ascending pipeline (6); the cooling water tank (2) is positioned outside the containment vessel (1); one end of the descending pipeline (3) is communicated with the bottom of the cooling water tank (2), and the other end of the descending pipeline is communicated with the side surface of the bottom of the cooling cover (7); one end of the ascending pipeline (6) is communicated with the bottom of the cooling water tank (2), and the other end of the ascending pipeline is communicated with the side face of the top of the cooling cover (7).
3. The passive steel containment vessel heat removal system of claim 2, wherein: the position of the cooling water tank (2) is higher than the top of the annular cavity (5).
4. The passive steel containment vessel heat removal system of claim 3, wherein: the top of the cooling water tank (2) is communicated with the external atmosphere.
5. The passive steel containment vessel heat removal system of claim 4, wherein: the diameters of the ascending pipeline (6) and the descending pipeline (3) are different.
6. The passive steel containment vessel heat removal system of claim 5, wherein: the control valve (4) is arranged on the descending pipeline (3), the control valve (4) can be opened according to a containment pressure signal or according to an opening instruction of an operator, and is communicated with the descending pipeline (3), so that the cooling water flows through the descending pipeline (3), the annular cavity (5) and the ascending pipeline (6) from the cooling water tank (2) in sequence and finally returns to the cooling water tank (2).
7. The passive steel containment vessel heat removal system of claim 6, wherein: the cooling water loops are uniformly arranged on the cooling cover (7).
8. The passive steel containment vessel heat removal system of claim 1, wherein:
the cooling water loop can inject cooling water into the annular cavity (5) from the bottom of the cooling cover (7) by means of gravity;
the cooling water after absorbing heat in the annular cavity (5) can flow back to the cooling water loop from the top of the cooling cover (7) by means of a gravity head formed by fluid density difference.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
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| CN202110752630.4A CN113593733A (en) | 2021-07-02 | 2021-07-02 | Passive steel containment heat exporting system |
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| Application Number | Priority Date | Filing Date | Title |
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| CN202110752630.4A CN113593733A (en) | 2021-07-02 | 2021-07-02 | Passive steel containment heat exporting system |
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| CN113593733A true CN113593733A (en) | 2021-11-02 |
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| CN202110752630.4A Pending CN113593733A (en) | 2021-07-02 | 2021-07-02 | Passive steel containment heat exporting system |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114038589A (en) * | 2021-11-10 | 2022-02-11 | 中国核动力研究设计院 | Full-passive reactor cavity water injection cooling system and method |
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| CN104217773A (en) * | 2014-07-30 | 2014-12-17 | 中国核电工程有限公司 | Nuclear power plant steel safe containment vessel heat-conductive device |
| CN105280249A (en) * | 2015-09-16 | 2016-01-27 | 中广核工程有限公司 | Nuclear power plant reactor pressure vessel and shield walling composite structure |
| CN106104701A (en) * | 2014-07-24 | 2016-11-09 | 哈尔滨工程大学 | Containment cooling system and containment combine cooling system with reactor pressure vessel |
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2021
- 2021-07-02 CN CN202110752630.4A patent/CN113593733A/en active Pending
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN103377728A (en) * | 2012-04-27 | 2013-10-30 | 上海核工程研究设计院 | Flooded-type containment complete passive after-heat removal system |
| CN202584748U (en) * | 2012-05-24 | 2012-12-05 | 国家核电技术有限公司 | Heat removal system for containment vessel of nuclear power station |
| CN104103325A (en) * | 2014-07-24 | 2014-10-15 | 哈尔滨工程大学 | Heat derivation system for long-term passive containment |
| CN106104701A (en) * | 2014-07-24 | 2016-11-09 | 哈尔滨工程大学 | Containment cooling system and containment combine cooling system with reactor pressure vessel |
| CN104217773A (en) * | 2014-07-30 | 2014-12-17 | 中国核电工程有限公司 | Nuclear power plant steel safe containment vessel heat-conductive device |
| CN105280249A (en) * | 2015-09-16 | 2016-01-27 | 中广核工程有限公司 | Nuclear power plant reactor pressure vessel and shield walling composite structure |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114038589A (en) * | 2021-11-10 | 2022-02-11 | 中国核动力研究设计院 | Full-passive reactor cavity water injection cooling system and method |
| CN114038589B (en) * | 2021-11-10 | 2024-02-13 | 中国核动力研究设计院 | Full passive reactor cavity water injection cooling system and method |
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