WO2014086274A1 - Vertical connection type surge pipe for voltage stabilizer of pressurized water reactor nuclear power plant - Google Patents
Vertical connection type surge pipe for voltage stabilizer of pressurized water reactor nuclear power plant Download PDFInfo
- Publication number
- WO2014086274A1 WO2014086274A1 PCT/CN2013/088417 CN2013088417W WO2014086274A1 WO 2014086274 A1 WO2014086274 A1 WO 2014086274A1 CN 2013088417 W CN2013088417 W CN 2013088417W WO 2014086274 A1 WO2014086274 A1 WO 2014086274A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- section
- vertical
- nuclear power
- surge pipe
- voltage stabilizer
- Prior art date
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 9
- 239000003381 stabilizer Substances 0.000 title claims abstract 5
- 238000013517 stratification Methods 0.000 abstract description 9
- 230000000694 effects Effects 0.000 abstract description 3
- 238000003466 welding Methods 0.000 abstract 2
- 239000000945 filler Substances 0.000 abstract 1
- 239000002826 coolant Substances 0.000 description 8
- 238000012986 modification Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000001186 cumulative effect Effects 0.000 description 1
- 230000032798 delamination Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 230000008646 thermal stress Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/032—Joints between tubes and vessel walls, e.g. taking into account thermal stresses
-
- 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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
-
- 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
Definitions
- the invention belongs to the technical field of nuclear power, and particularly relates to a surge tube of a voltage regulator.
- the regulator surge tube (hereinafter referred to as the surge tube) has one end connected to the hot section of a loop of the reactor coolant system, and the other end is connected to the lower head of the regulator to deliver the reactor coolant under high temperature, high pressure and strong radioactive conditions, and Other equipment and piping together form the pressure boundary and are one of the most important pipelines in the reactor coolant system.
- the coolant temperature in the regulator is higher than the temperature in the reactor coolant system, the coolant temperature from the reactor coolant system is low and density during steady state operation of the plant. Large, occupying the lower part of the surge tube; the coolant from the regulator has a high temperature and a low density, occupying the upper part of the surge tube.
- the above phenomenon is called the thermal stratification phenomenon of the fluctuation tube.
- the surge tube of PWR nuclear power plant generally adopts a close horizontal arrangement (the elevation angle is only 17 '), so there is a serious thermal stratification on the radial section of the pipeline, and the main body of the corrugated pipe and its key welds (especially fluctuations) The weld at the junction of the tube and the main circuit) causes severe thermal stress effects.
- the thermal stratification of fluctuating pipes has always been one of the factors that threaten the safety of power plants, and it is also a key issue of concern to the National Nuclear Safety Administration.
- the cumulative use factor of the fluctuating tube fatigue is already close to the limit.
- the object of the present invention is to provide a vertically connected wave tube of a pressurized water reactor nuclear power plant voltage regulator, which can effectively relieve the thermal stratification phenomenon to the wave tube and its main pipe nozzle while effectively connecting the voltage regulator to the main circuit.
- the impact of the office is as follows:
- a vertically connected wave tube of a pressurized water reactor nuclear power plant voltage regulator comprising a vertical section I, a vertical section II, and an extension between the two, the vertical section I from the main loop pipeline
- the top is vertically vertical
- the vertical section II is vertically connected to the bottom of the regulator, and the extension extends upward at an elevation angle of 2 to 5° from the horizontal plane.
- the extension section is composed of a straight pipe section, a curved section I, a curved section II and a semicircular section; one end of the straight pipe section and the top of the main circuit pipe Vertically connected, the other end of the straight pipe section is connected with the curved section I; the semicircular section is located between the curved section I and the curved section II; one end of the curved section II is vertically connected to the bottom of the regulator, and is bent The other end of the segment II is connected to the semicircular segment.
- the beneficial effects obtained by the invention are as follows:
- the vertical section of the design is used to make the wave tube directly out of the main pipe, so that there is no thermal stratification on the weld of the wave tube nozzle on the main pipe;
- the extension of the middle section of the wave tube The upward extension of the inclination angle of 2 ⁇ 5° effectively alleviates the influence of the thermal stratification effect on the weld of the section.
- Figure 1 is a side view of a vertically connected surge tube of a pressurized water reactor nuclear power plant regulator
- Figure 2 is a plan view of Figure 1;
- the wave tube includes two vertical segments, a vertical segment I 1 and a vertical segment 112, and includes The extension 3 between the two vertical sections 1 and 2, the vertical section I 1 is vertically detached from the top of the main circuit duct, so that there is no thermal delamination on the weld section of the section, thereby ensuring the main The safety and operational life of the pipe running after it is connected.
- the other vertical section ⁇ 2 is vertically connected to the bottom of the regulator to achieve communication between the main circuit and the regulator.
- the extension 3 between the vertical sections 1 and 2 and the horizontal plane are optimally selected at an elevation angle of 2.5°, and the curved extension is inclined upward, maintaining the inclination angle, and the slope is sufficiently large to effectively control the influence of the thermal stratification on the extension 3 of the wave tube. .
- the design of the extension section 3 adopts an optimum form.
- the extension section 3 is composed of four parts, a straight pipe section 301, a curved section 1303 and a curved section 11304, and a curved section I303.
- the semicircular section 302 between the curved section II 304 and the four sections constitute a section of the tube which approximates the omega shape.
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)
- Structures Of Non-Positive Displacement Pumps (AREA)
Abstract
Description
Claims
Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB1511704.7A GB2523706B (en) | 2012-12-06 | 2013-12-03 | Vertical connection type surge pipe for pressurizer of pressurized water reactor nuclear power plant |
ZA2015/04856A ZA201504856B (en) | 2012-12-06 | 2015-07-06 | Vertical connection type surge pipe for pressurizer of pressurized water reactor nuclear power plant |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201210519796.2 | 2012-12-06 | ||
CN201210519796.2A CN103854709A (en) | 2012-12-06 | 2012-12-06 | Vertical connection type surge pipe for pressurized water reactor nuclear power plant voltage stabilizer |
Publications (1)
Publication Number | Publication Date |
---|---|
WO2014086274A1 true WO2014086274A1 (en) | 2014-06-12 |
Family
ID=50862256
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/CN2013/088417 WO2014086274A1 (en) | 2012-12-06 | 2013-12-03 | Vertical connection type surge pipe for voltage stabilizer of pressurized water reactor nuclear power plant |
Country Status (5)
Country | Link |
---|---|
CN (1) | CN103854709A (en) |
AR (1) | AR093808A1 (en) |
GB (1) | GB2523706B (en) |
WO (1) | WO2014086274A1 (en) |
ZA (1) | ZA201504856B (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN108806808A (en) * | 2018-07-11 | 2018-11-13 | 上海核工程研究设计院有限公司 | A kind of stub (tube) with supporting block formula main pipeline |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN109798510A (en) * | 2019-01-11 | 2019-05-24 | 中广核工程有限公司 | A kind of main feed water pipe device for pressurized water reactor nuclear power station steam generator |
Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN201383351Y (en) * | 2009-03-24 | 2010-01-13 | 中广核工程有限公司 | Thermal stratification elimination device used for nuclear power station |
KR20100062174A (en) * | 2008-12-01 | 2010-06-10 | 현대자동차주식회사 | Valance shaft mounting system |
CN102760500A (en) * | 2012-07-02 | 2012-10-31 | 西安交通大学 | Surge wave pipe structure of nuclear power station voltage stabilizer |
CN202650567U (en) * | 2012-03-23 | 2013-01-02 | 中广核工程有限公司 | Pressurizer surge line for nuclear power plant |
CN102996908A (en) * | 2012-11-12 | 2013-03-27 | 华北电力大学 | Pipeline capable of reducing influence of thermal stratification |
CN203026164U (en) * | 2012-12-06 | 2013-06-26 | 中国核动力研究设计院 | Vertical connection type surge pipe for voltage stabilizer of pressurized water reactor nuclear power plant |
Family Cites Families (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2438776A1 (en) * | 1973-08-22 | 1975-03-06 | Combustion Eng | NUCLEAR REACTOR WITH PUMPS FOR THE COOLANT CIRCULATION |
DE2951458C2 (en) * | 1979-12-20 | 1983-01-05 | Kraftwerk Union AG, 4330 Mülheim | surge tank |
JPS62217198A (en) * | 1986-03-19 | 1987-09-24 | 株式会社日立製作所 | Pressurizer connection structure of pressurized water type reactor |
-
2012
- 2012-12-06 CN CN201210519796.2A patent/CN103854709A/en active Pending
-
2013
- 2013-12-03 GB GB1511704.7A patent/GB2523706B/en active Active
- 2013-12-03 WO PCT/CN2013/088417 patent/WO2014086274A1/en active Application Filing
- 2013-12-05 AR ARP130104508A patent/AR093808A1/en active IP Right Grant
-
2015
- 2015-07-06 ZA ZA2015/04856A patent/ZA201504856B/en unknown
Patent Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
KR20100062174A (en) * | 2008-12-01 | 2010-06-10 | 현대자동차주식회사 | Valance shaft mounting system |
CN201383351Y (en) * | 2009-03-24 | 2010-01-13 | 中广核工程有限公司 | Thermal stratification elimination device used for nuclear power station |
CN202650567U (en) * | 2012-03-23 | 2013-01-02 | 中广核工程有限公司 | Pressurizer surge line for nuclear power plant |
CN102760500A (en) * | 2012-07-02 | 2012-10-31 | 西安交通大学 | Surge wave pipe structure of nuclear power station voltage stabilizer |
CN102996908A (en) * | 2012-11-12 | 2013-03-27 | 华北电力大学 | Pipeline capable of reducing influence of thermal stratification |
CN203026164U (en) * | 2012-12-06 | 2013-06-26 | 中国核动力研究设计院 | Vertical connection type surge pipe for voltage stabilizer of pressurized water reactor nuclear power plant |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN108806808A (en) * | 2018-07-11 | 2018-11-13 | 上海核工程研究设计院有限公司 | A kind of stub (tube) with supporting block formula main pipeline |
Also Published As
Publication number | Publication date |
---|---|
GB2523706B (en) | 2017-12-06 |
GB201511704D0 (en) | 2015-08-19 |
AR093808A1 (en) | 2015-06-24 |
CN103854709A (en) | 2014-06-11 |
GB2523706A (en) | 2015-09-02 |
ZA201504856B (en) | 2017-04-26 |
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