CN106024076A - Device for reducing risk of pressure relief tank compartment of nuclear power plant - Google Patents
Device for reducing risk of pressure relief tank compartment of nuclear power plant Download PDFInfo
- Publication number
- CN106024076A CN106024076A CN201610329850.5A CN201610329850A CN106024076A CN 106024076 A CN106024076 A CN 106024076A CN 201610329850 A CN201610329850 A CN 201610329850A CN 106024076 A CN106024076 A CN 106024076A
- Authority
- CN
- China
- Prior art keywords
- pressure relief
- nuclear power
- power plant
- containment
- compartment
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/001—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices against explosions, e.g. blast shields
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/004—Pressure suppression
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
本发明涉及一种用于降低核电厂卸压箱隔间风险的装置,该装置包括通过连接管(12)与卸压箱爆破阀(7)相连的排气管道(2),所述排气管道(2)延伸至反应堆安全壳内的上部空间,且所述排气管道(2)的排气口位于反应堆安全壳上部空间且远离安全壳壁面。本发明提供的装置,其结构简单,造价低,便于安装维护,且该装置能够将卸压箱排放的水蒸气、氢气引导到安全壳大空间,避免氢气在卸压箱隔间的集聚,防止局部氢气爆炸导致的安全壳失效。
The invention relates to a device for reducing the risk of a pressure relief tank compartment in a nuclear power plant, which comprises an exhaust pipe (2) connected to a pressure relief tank burst valve (7) through a connecting pipe (12), the exhaust The pipe (2) extends to the upper space in the reactor containment, and the exhaust port of the exhaust pipe (2) is located in the upper space of the reactor containment and away from the wall of the containment. The device provided by the invention has simple structure, low cost, and is easy to install and maintain, and the device can guide the water vapor and hydrogen discharged from the pressure relief tank to the large space of the containment, avoiding the accumulation of hydrogen in the compartment of the pressure relief tank, preventing Containment failure due to localized hydrogen explosion.
Description
技术领域technical field
本发明属于核电站安全系统配置技术领域,具体涉及一种用于降低核电厂卸压箱隔间风险的装置。The invention belongs to the technical field of nuclear power plant safety system configuration, and in particular relates to a device for reducing the risk of a pressure relief box compartment of a nuclear power plant.
背景技术Background technique
卸压箱是核电站用来收集一回路安全阀排放的水蒸气的装置,如图1所示,卸压箱6通常设在安全壳中下部的卸压箱隔间5中,卸压箱6上连接有卸压管路10,卸压管路10通过安全阀9和稳压器8相连,此外,卸压箱6顶部还连接有卸压箱爆破阀7(见图3)。在设计基准事故下,一回路发生瞬态或者小破口事故时,一回路压力上升,超过稳压器8上的安全阀9的开启压力后,安全阀9自动开启,从而将一回路冷却水通过卸压管路10排放至卸压箱6。当核电厂发生严重事故后,为了避免一回路在高压下发生压力容器失效,通常要通过稳压器安全阀或者快速卸压阀进行一回路卸压,这个过程中一回路冷却剂排放到卸压箱6中。卸压箱6能够将一定量的水、水蒸气保持在卸压箱6内,避免带有放射性的一回路冷却水进入安全壳。The pressure relief box is a device used by nuclear power plants to collect the water vapor discharged from the safety valve of the primary circuit. As shown in Figure 1, the pressure relief box 6 is usually located in the pressure relief box compartment 5 in the middle and lower part of the containment. A pressure relief pipeline 10 is connected, and the pressure relief pipeline 10 is connected with a pressure stabilizer 8 through a safety valve 9. In addition, the top of the pressure relief box 6 is also connected with a pressure relief box burst valve 7 (see FIG. 3 ). Under the design basis accident, when a transient or a small breach accident occurs in the primary circuit, the pressure of the primary circuit rises and exceeds the opening pressure of the safety valve 9 on the voltage stabilizer 8, and the safety valve 9 automatically opens, so that the cooling water of the primary circuit It is discharged to the pressure relief tank 6 through the pressure relief line 10. When a serious accident occurs in a nuclear power plant, in order to avoid the failure of the pressure vessel in the primary circuit under high pressure, the pressure relief of the primary circuit is usually performed through the safety valve of the regulator or the quick pressure relief valve. During this process, the coolant in the primary circuit is discharged to the pressure relief Box 6. The pressure relief box 6 can keep a certain amount of water and water vapor in the pressure relief box 6 to prevent the radioactive primary circuit cooling water from entering the containment.
但是,当卸压箱6由于内部压力过高时,其顶部的卸压箱爆破阀7会自动打开,将一回路冷却剂排放到安全壳内。在严重事故过程中,由于过热的锆包壳会和水蒸气发生锆水反应,会产生大量的氢气,这些氢气通过稳压器安全阀或者快速卸压阀进入卸压箱6后,通过卸压箱爆破阀7进入卸压箱6所在的卸压箱隔间5。由于卸压箱隔间5位于安全壳中下部,空气流通性差,因此会导致卸压箱隔间5内出现较高的氢气浓度,有可能发生局部的氢气燃烧甚至爆炸,进而威胁安全壳的完整性,造成大量放射性物质向环境释放。However, when the internal pressure of the pressure relief box 6 is too high, the burst valve 7 on the top of the pressure relief box will be automatically opened to discharge the primary circuit coolant into the containment. During a serious accident, due to the zirconium water reaction between the overheated zirconium cladding and water vapor, a large amount of hydrogen gas will be generated. The tank blast valve 7 enters the pressure relief tank compartment 5 where the pressure relief tank 6 is located. Since the pressure relief box compartment 5 is located in the middle and lower part of the containment vessel, the air circulation is poor, which will lead to a high hydrogen concentration in the pressure relief box compartment 5, and local hydrogen combustion or even explosion may occur, thereby threatening the integrity of the containment vessel. , resulting in the release of large amounts of radioactive material to the environment.
发明内容Contents of the invention
针对现有技术中存在的缺陷,本发明的目的是提供一种用于降低核电厂卸压箱隔间氢气燃烧、爆炸风险的装置,该装置结构简单,造价低,便于安装维护,能够将卸压箱排放的水蒸气、氢气引导到安全壳大空间,避免氢气在卸压箱隔间的集聚,防止局部氢气爆炸导致的安全壳失效。In view of the defects existing in the prior art, the object of the present invention is to provide a device for reducing the risk of hydrogen combustion and explosion in the pressure relief box compartment of a nuclear power plant. The device has a simple structure, low cost, and is easy to install and maintain. The water vapor and hydrogen gas discharged from the pressure tank are guided to the large space of the containment vessel, so as to avoid the accumulation of hydrogen gas in the compartment of the decompression tank and prevent the failure of the containment vessel caused by local hydrogen explosion.
为达到以上目的,本发明采用的技术方案是:一种用于降低核电厂卸压箱隔间风险的装置,其中,用于放置卸压箱的卸压箱隔间设在核电厂反应堆安全壳的中下部,所述卸压箱上连接有卸压管路,卸压管路通过安全阀和稳压器相连,卸压箱顶部还连接有卸压箱爆破阀,所述的用于降低核电厂卸压箱隔间风险的装置包括通过连接管与卸压箱爆破阀顶部相连的排气管道,所述排气管道延伸至反应堆安全壳内的上部空间,且所述排气管道的排气口位于反应堆安全壳上部空间且远离安全壳壁面。In order to achieve the above purpose, the technical solution adopted by the present invention is: a device for reducing the risk of the pressure relief box compartment of a nuclear power plant, wherein the pressure relief box compartment for placing the pressure relief box is located in the reactor containment of the nuclear power plant In the middle and lower part of the pressure relief box, a pressure relief pipeline is connected to the pressure relief box, and the pressure relief pipeline is connected to the voltage stabilizer through a safety valve. The top of the pressure relief box is also connected to a burst valve of the pressure relief box. The device for the risk of the pressure relief box compartment of the plant includes an exhaust pipe connected to the top of the burst valve of the pressure relief box through a connecting pipe, the exhaust pipe extends to the upper space in the reactor containment, and the exhaust pipe of the exhaust pipe The mouth is located in the upper space of the reactor containment vessel and away from the wall of the containment vessel.
进一步,连接管下部与爆破阀相连,连接管上部通过连接法兰与排气管道相连。Further, the lower part of the connecting pipe is connected with the blasting valve, and the upper part of the connecting pipe is connected with the exhaust pipe through the connecting flange.
进一步,所述排气管道的排气口上设有盖板。Further, the exhaust port of the exhaust duct is provided with a cover plate.
进一步,排气管道通过若干管道支撑组件固定在安全壳内的结构墙体上。Further, the exhaust pipe is fixed on the structural wall inside the containment shell through several pipe support components.
本发明提供的用于降低核电厂卸压箱隔间风险的装置可以消除由于卸压箱隔间的氢气集聚导致的氢气局部燃爆风险,并且本装置结构简单、造价低,便于安装维护,既能够应用与新设计的核电厂,也可以用于已建成核电厂的技术改造,从而提高核电厂的安全性。The device provided by the present invention for reducing the risk of the compartment of the pressure relief tank in a nuclear power plant can eliminate the risk of partial hydrogen explosion caused by the accumulation of hydrogen in the compartment of the pressure relief tank, and the device has a simple structure, low cost, and is convenient for installation and maintenance. It can be applied to newly designed nuclear power plants, and can also be used for technical transformation of existing nuclear power plants, thereby improving the safety of nuclear power plants.
附图说明Description of drawings
图1是本发明提供的一种用于降低核电厂卸压箱隔间风险的装置的结构示意图;Fig. 1 is a kind of structural schematic diagram of the device for reducing the risk of nuclear power plant pressure relief box compartment provided by the present invention;
图2是图1中排气管道、连接管与卸压箱爆破阀的连接示意图;Fig. 2 is a schematic diagram of the connection of the exhaust pipe, the connecting pipe and the blasting valve of the pressure relief box in Fig. 1;
图3是现有卸压箱爆破阀与卸压箱的连接示意图。Fig. 3 is a schematic diagram of the connection between the blast valve of the existing pressure relief box and the pressure relief box.
具体实施方式detailed description
下面结合附图和具体实施方式对本发明作进一步描述。The present invention will be further described below in conjunction with the accompanying drawings and specific embodiments.
如图1所述,本发明涉及的卸压箱6设在反应堆安全壳内的卸压箱隔间5中,卸压箱6上连接有卸压管道10,卸压管道10通过安全阀9和稳压器8相连,卸压箱6顶部还连接有卸压箱爆破阀7。As shown in Figure 1, the pressure relief box 6 involved in the present invention is arranged in the pressure relief box compartment 5 in the reactor containment, the pressure relief box 6 is connected with a pressure relief pipeline 10, and the pressure relief pipeline 10 passes through the safety valve 9 and The voltage stabilizer 8 is connected, and the top of the pressure relief box 6 is also connected with a burst valve 7 of the pressure relief box.
本发明提供的一种用于降低核电厂卸压箱隔间风险的装置包括通过连接管12与卸压箱爆破阀7相连的排气管道2,所述排气管道2延伸至反应堆安全壳内的上部空间,所述排气管道2的排气口位于反应堆安全壳上部空间且远离安全壳壁面。A device for reducing the risk of the pressure relief tank compartment of a nuclear power plant provided by the present invention includes an exhaust pipe 2 connected to the explosion valve 7 of the pressure relief box through a connecting pipe 12, and the exhaust pipe 2 extends into the reactor containment The upper space of the exhaust pipe 2 is located in the upper space of the reactor containment and away from the wall of the containment.
本发明中,连接管12下部与卸压箱爆破阀7相连。连接管12上部通过连接法兰1与排气管道2相连,方便检修。In the present invention, the lower part of the connecting pipe 12 is connected with the burst valve 7 of the pressure relief box. The upper part of the connecting pipe 12 is connected to the exhaust pipe 2 through the connecting flange 1, which is convenient for maintenance.
另外,排气管道2的排气口上可设盖板3,防止喷淋水及异物进入排气管道2。In addition, a cover plate 3 may be provided on the exhaust port of the exhaust pipe 2 to prevent spray water and foreign matters from entering the exhaust pipe 2 .
优选情况下,本发明中的排气管道2可通过若干管道支撑组件4固定在安全壳内的结构墙体11上,防止发生由于卸压箱爆破阀7喷射而导致的管道位移。Preferably, the exhaust pipeline 2 in the present invention can be fixed on the structural wall 11 inside the containment by several pipeline support assemblies 4 to prevent pipeline displacement caused by the injection of the burst valve 7 of the pressure relief box.
核电站正常运行下,排气管道2出口端的盖板3关闭。在事故工况下,当卸压箱爆破阀7开启后,大量的水蒸气、氢气通过卸压箱爆破阀7进入排气管道2,同时盖板3在气流冲击下自动打开,将大量的水蒸气、氢气排放到安全壳上部大空间,从而避免氢气在卸压箱隔间5内积聚,防止局部氢气爆炸导致的安全壳失效。Under normal operation of the nuclear power plant, the cover plate 3 at the outlet end of the exhaust pipe 2 is closed. Under accident conditions, when the burst valve 7 of the pressure relief box is opened, a large amount of water vapor and hydrogen enter the exhaust pipe 2 through the burst valve 7 of the pressure relief box. The steam and hydrogen are discharged to the large space above the containment, so as to avoid the accumulation of hydrogen in the compartment 5 of the pressure relief box, and prevent the failure of the containment caused by the partial hydrogen explosion.
本发明所述结构并不限于具体实施方式中所述的实施例,本领域技术人员根据本发明的技术方案得出其他的实施方式,同样属于本发明的技术创新范围。The structures described in the present invention are not limited to the examples described in the specific implementation manners. Those skilled in the art can obtain other implementation manners according to the technical solutions of the present invention, which also belong to the technical innovation scope of the present invention.
Claims (4)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610329850.5A CN106024076B (en) | 2016-05-18 | 2016-05-18 | A device for reducing the risk of a pressure relief tank compartment in a nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610329850.5A CN106024076B (en) | 2016-05-18 | 2016-05-18 | A device for reducing the risk of a pressure relief tank compartment in a nuclear power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN106024076A true CN106024076A (en) | 2016-10-12 |
| CN106024076B CN106024076B (en) | 2019-11-08 |
Family
ID=57098376
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201610329850.5A Active CN106024076B (en) | 2016-05-18 | 2016-05-18 | A device for reducing the risk of a pressure relief tank compartment in a nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN106024076B (en) |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4086308A (en) * | 1975-02-18 | 1978-04-25 | Siemens Aktiengesellschaft | Pressurized relief tank for steam |
| EP0205900A2 (en) * | 1985-06-26 | 1986-12-30 | Westinghouse Electric Corporation | Pressure control system for a pressurized water nuclear reactor plant |
| US4692297A (en) * | 1985-01-16 | 1987-09-08 | Westinghouse Electric Corp. | Control of nuclear reactor power plant on occurrence of rupture in coolant tubes |
| CN102169731A (en) * | 2011-02-14 | 2011-08-31 | 中国核电工程有限公司 | Device and method for quickly relieving pressure in primary circuit of pressurized water reactor nuclear power plant |
| CN103871490A (en) * | 2012-12-14 | 2014-06-18 | 中国核动力研究设计院 | Pressure-relief apparatus applied for pressurized water reactor nuclear power plant pressurizer pressure-relief box |
| CN103971762A (en) * | 2014-05-05 | 2014-08-06 | 中广核(北京)仿真技术有限公司 | Containment vessel for nuclear power plant |
-
2016
- 2016-05-18 CN CN201610329850.5A patent/CN106024076B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4086308A (en) * | 1975-02-18 | 1978-04-25 | Siemens Aktiengesellschaft | Pressurized relief tank for steam |
| US4692297A (en) * | 1985-01-16 | 1987-09-08 | Westinghouse Electric Corp. | Control of nuclear reactor power plant on occurrence of rupture in coolant tubes |
| EP0205900A2 (en) * | 1985-06-26 | 1986-12-30 | Westinghouse Electric Corporation | Pressure control system for a pressurized water nuclear reactor plant |
| CN102169731A (en) * | 2011-02-14 | 2011-08-31 | 中国核电工程有限公司 | Device and method for quickly relieving pressure in primary circuit of pressurized water reactor nuclear power plant |
| CN103871490A (en) * | 2012-12-14 | 2014-06-18 | 中国核动力研究设计院 | Pressure-relief apparatus applied for pressurized water reactor nuclear power plant pressurizer pressure-relief box |
| CN103971762A (en) * | 2014-05-05 | 2014-08-06 | 中广核(北京)仿真技术有限公司 | Containment vessel for nuclear power plant |
Non-Patent Citations (1)
| Title |
|---|
| 蒋国元 主编: "《WWER-1000核电厂系统与设备》", 30 September 2009, 北京:原子能出版社 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN106024076B (en) | 2019-11-08 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US9697914B2 (en) | Nuclear power plant and passive containment cooling system | |
| CN105321584B (en) | Containment vessel for water cooled moderated nuclear reactor | |
| KR102580625B1 (en) | Passive cooling for cold shutdown | |
| CN101855675B (en) | Method for water filling and air blow-off of the main primary circuit of a nuclear unit and cover for implementing said method | |
| CN101783187B (en) | A method for exhausting the main system of a nuclear reactor | |
| CN104078085B (en) | A kind of built-in material-changing water tank of containment with water scrub function | |
| CN205104238U (en) | Built -in steam stabiliser | |
| JP6632081B2 (en) | Containment vessel drain system | |
| GB2520456A (en) | Combined active and passive containment vessel heat removal apparatus | |
| GB2535848A (en) | Secondary side passive waste heat removal system | |
| CN106328216A (en) | Water seal device for nuclear power plant voltage stabilizer and nuclear power plant voltage stabilizer | |
| CN103187108B (en) | A kind of top is with double-deck integral reactor | |
| CN203366752U (en) | Passive pressurized water reactor depressurizing system | |
| KR101224024B1 (en) | Passive containment cooling system using passive auxiliary feed-water system and irwst | |
| CN106024076B (en) | A device for reducing the risk of a pressure relief tank compartment in a nuclear power plant | |
| JP5687440B2 (en) | Reactor containment heat removal apparatus and heat removal method | |
| CN204905147U (en) | Transformer buchholz relay with air bleeder | |
| KR102214119B1 (en) | Coolant recirculation system of nuclear power plant | |
| CN104103326A (en) | Device used for sealing detection on containment outer isolation valve | |
| CN113593731B (en) | Passive containment depressurization filtration system | |
| CN209388717U (en) | Nuclear power station safety total system | |
| CN203223345U (en) | Water injection vacuum set with condensation function | |
| CN205279049U (en) | Hydrophobic flash vessel of steam of anti soda erosion | |
| JP2005345158A (en) | Boiling water reactor facility renewal method and boiling water reactor facility | |
| CN223006572U (en) | Passive pressure relief device and reactor pressure relief safety system |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |