CN103187113B - A kind of nuclear power station steam generator steam flow restriction device - Google Patents
A kind of nuclear power station steam generator steam flow restriction device Download PDFInfo
- Publication number
- CN103187113B CN103187113B CN201310017919.7A CN201310017919A CN103187113B CN 103187113 B CN103187113 B CN 103187113B CN 201310017919 A CN201310017919 A CN 201310017919A CN 103187113 B CN103187113 B CN 103187113B
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- steam
- flow restriction
- restriction device
- nuclear power
- power station
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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
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- Monitoring And Testing Of Nuclear Reactors (AREA)
- Jet Pumps And Other Pumps (AREA)
Abstract
The present invention provides a kind of nuclear power station steam generator steam flow restriction device reducing the steam flow restriction device pressure loss, and it arranges 19 Venturi tubes inside steam (vapor) outlet ozzle；This 19 Venturi tube arranged modes are：One Venturi tube of center arrangement, mesosphere arranges 6 Venturi tubes, and outmost turns arrange 12 Venturi tubes.A kind of nuclear power station steam generator steam flow restriction device proposed by the present invention, compared with traditional steam flow restriction device, the present invention has the characteristics that lower pressure loss, can improve the outlet vapor pressure of steam generator, thus improving economy.
Description
Technical field
The present invention relates to nuclear power station steam generator technical field is and in particular to a kind of nuclear power station steam generation
Device steam flow restriction device.
Background technology
Steam generator is one of key equipment of pressurized-water reactor nuclear power plant.PWR steam generator steam limits
Stream device is mounted in a kind of device on steam generator outlet ozzle.Its effect is that steam is occurring
During system depressurisation accident（As main steam line ruptures, relief valve or pressure-relief valve are surprisingly opened）, steam is sent out
The steam flow of raw device limits within the specific limits, to avoid reactor significantly over loading, causes cooling
Agent temperature reduces, thus leading to reactivity to increase suddenly, and avoids that steam water interface flow velocity is too high to be led to steam
Vapour generator internals are damaged and containment pressure rapid increase.During normal operation, because steam passes through steam
There is the pressure loss in current-limiting apparatus, therefore it is required that steam flow restriction device pressure loss in normal operation is less.
Steam flow restriction device is typically made up of several Venturi tubes.
Traditional steam flow restriction device is made up of seven Venturi tubes, such as one phase of Qinshan steam generator, the Qin
Mountain second phase steam generator, AP1000 steam generator etc., as shown in Figure 3.Its advantage is that structure is tight
Gather, shortcoming is that the pressure loss is larger.
Content of the invention
It is an object of the invention to provide a kind of nuclear power station steam reducing the steam flow restriction device pressure loss is sent out
Raw device steam flow restriction device.
Realize the technical scheme of the object of the invention：A kind of nuclear power station steam generator steam flow restriction device, its
19 Venturi tubes are set inside steam (vapor) outlet ozzle；This 19 Venturi tube arranged modes are：
One Venturi tube of center arrangement, mesosphere arranges 6 Venturi tubes, and outmost turns arrange 12 venturi
Pipe.
A kind of nuclear power station steam generator steam flow restriction device as above, the larynx of its 19 Venturi tubes
The total circulation area in portion is less than limiting design value.
Effect of the invention is that：The present invention proposes a kind of nuclear power station steam generator steam flow restriction device,
Compared with traditional steam flow restriction device, the present invention has the characteristics that lower pressure loss, can improve steam
The outlet vapor pressure of generator, thus improve economy.
Brief description
Fig. 1 is steam generator sectional view（Top is steam (vapor) outlet ozzle and steam flow restriction device）
Fig. 2 is the I part partial enlarged drawing of Fig. 1（Steam (vapor) outlet ozzle and steam flow restriction device sectional view）；
Fig. 3 is traditional steam flow restriction structure drawing of device（Top view）；
Fig. 4 is steam flow restriction structure drawing of device of the present invention（Top view）.
In figure：1 steam (vapor) outlet ozzle；2 Venturi tubes.
Specific embodiment
Below in conjunction with the accompanying drawings with specific embodiment to a kind of nuclear power station steam generator steam of the present invention
Current-limiting apparatus are further described.
As shown in Figure 2 and Figure 4, a kind of nuclear power station steam generator steam flow restriction device of the present invention,
It arranges 19 Venturi tubes 2 inside steam (vapor) outlet ozzle 1.
This 19 Venturi tubes 2 arranged mode is：One Venturi tube 2 of center arrangement, mesosphere
6 Venturi tubes 2 of arrangement, outmost turns arrange 12 Venturi tubes 2.The throat of 19 Venturi tubes 2
Total circulation area is less than limiting design value.
During operation, flow through venturi 2 flows out steam generator to steam from bottom to top.During accident, due to civilian mound
In pipe 2 characteristic, can reach limit steam flow purpose.
Claims (1)
1. a kind of nuclear power station steam generator steam flow restriction device it is characterised in that：In steam (vapor) outlet ozzle
(1) 19 Venturi tubes (2) of internal setting；This 19 Venturi tube (2) arranged modes are：
One Venturi tube (2) of center arrangement, mesosphere arranges 6 Venturi tubes (2), outmost turns arrangement 12
Individual Venturi tube (2).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201310017919.7A CN103187113B (en) | 2013-01-18 | 2013-01-18 | A kind of nuclear power station steam generator steam flow restriction device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201310017919.7A CN103187113B (en) | 2013-01-18 | 2013-01-18 | A kind of nuclear power station steam generator steam flow restriction device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN103187113A CN103187113A (en) | 2013-07-03 |
| CN103187113B true CN103187113B (en) | 2017-03-01 |
Family
ID=48678241
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201310017919.7A Active CN103187113B (en) | 2013-01-18 | 2013-01-18 | A kind of nuclear power station steam generator steam flow restriction device |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN103187113B (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP3729465A4 (en) * | 2017-12-18 | 2021-09-08 | GE-Hitachi Nuclear Energy Americas LLC | Multiple-path flow restrictor nozzle |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4071403A (en) * | 1974-08-01 | 1978-01-31 | Westinghouse Electric Corporation | Method and apparatus for protecting the core of a nuclear reactor |
| KR20050007941A (en) * | 2003-07-12 | 2005-01-21 | 두산중공업 주식회사 | Method for Designing Multi-Venturi Nozzle of Steam Generator |
| CN203070792U (en) * | 2013-01-18 | 2013-07-17 | 上海核工程研究设计院 | Nuclear power plant steam generator steam flow limiter |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| SE430715B (en) * | 1982-04-28 | 1983-12-05 | Westinghouse Electric Corp | VIEWING AND INFORMATIONING OF SECONDARY WATER THROUGH AN INLET TO AN ANGGENERATERER |
-
2013
- 2013-01-18 CN CN201310017919.7A patent/CN103187113B/en active Active
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4071403A (en) * | 1974-08-01 | 1978-01-31 | Westinghouse Electric Corporation | Method and apparatus for protecting the core of a nuclear reactor |
| KR20050007941A (en) * | 2003-07-12 | 2005-01-21 | 두산중공업 주식회사 | Method for Designing Multi-Venturi Nozzle of Steam Generator |
| CN203070792U (en) * | 2013-01-18 | 2013-07-17 | 上海核工程研究设计院 | Nuclear power plant steam generator steam flow limiter |
Non-Patent Citations (1)
| Title |
|---|
| 秦山核电二期600MW蒸汽发生器关键焊接技术;邹小平 等;《锅炉技术》;20060731;第37卷(第4期);第5-6页 * |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP3729465A4 (en) * | 2017-12-18 | 2021-09-08 | GE-Hitachi Nuclear Energy Americas LLC | Multiple-path flow restrictor nozzle |
Also Published As
| Publication number | Publication date |
|---|---|
| CN103187113A (en) | 2013-07-03 |
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Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: Shanghai Nuclear Engineering Research & Design Institute |
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| CP01 | Change in the name or title of a patent holder | ||
| CP01 | Change in the name or title of a patent holder |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
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| CP01 | Change in the name or title of a patent holder |