GB2523706A - 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 PDF

Info

Publication number
GB2523706A
GB2523706A GB1511704.7A GB201511704A GB2523706A GB 2523706 A GB2523706 A GB 2523706A GB 201511704 A GB201511704 A GB 201511704A GB 2523706 A GB2523706 A GB 2523706A
Authority
GB
United Kingdom
Prior art keywords
section
vertical
surge pipe
nuclear power
power plant
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
Application number
GB1511704.7A
Other versions
GB2523706B (en
GB201511704D0 (en
Inventor
Wei Huang
Haiming Sui
Rongfu Su
Xianghong Liu
Baoping Wang
Jianyong Lai
Yun Ren
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Nuclear Power Institute of China
Original Assignee
Nuclear Power Institute of China
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Nuclear Power Institute of China filed Critical Nuclear Power Institute of China
Publication of GB201511704D0 publication Critical patent/GB201511704D0/en
Publication of GB2523706A publication Critical patent/GB2523706A/en
Application granted granted Critical
Publication of GB2523706B publication Critical patent/GB2523706B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • 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
    • 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
    • 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

A vertical connection type surge pipe for a voltage stabilizer of a pressurized water reactor nuclear power plant comprises a vertical section I (1), a vertical section II (2) and an extension section (3) between the two. The vertical section I is vertically connected outside from the top part of a main loop pipeline; the vertical section II is vertically connected upwards with the bottom of a voltage stabilizer; and the extension section extends upwards at an elevation angle of 2-5 degrees with the horizontal plane. By using the vertical sections, the surge pipe is vertically connected outside from a main pipeline, so that the thermal stratification influence on a welding line of a filler neck of the surge pipe on the main pipeline is avoided; and as the extension section in the middle section of the surge pipe extends upwards at the elevation angle of 2-5 degrees, the influence of the thermal stratification effect on the welding line is effectively relieved.

Description

Specification
Vertical Connection Type Surge Pipe for Pressurizer of Pressurized Water Reactor Nuclear Power Plant Technical Held S The present invention belongs to the field of nuclear power technology, specifically to a surge pipe fix pressurizer
Background Art
One end of the surge pipe for pressurizer (hereinafter referred to as surge pipe) is connected with a hot pipe section of a ioop of the reactor coolant system it and the other end is connected with the lower plug of the pressurizer to transport reactor coolant in the condition of high temperature. high pressure and strong radioactivity and form pressure boundary together with other equipment and piping as one of the important pipes for reactor coolant system.
During the operation of PWR nuclear power plant, the temperature of the coolant in i:he pressurizer is higher than that of the reactor coolant system, Thus, in the case of steadystate operation of the nuclear power plant, the coolant from the reactor coolant system is featured in low temperature and high density, occupying the lower part of the surge pipe while the coolant from the pressurizer is featured in high teniperature and low density; occupying the upper part of the surge pipe. In engineering, this phenomenon is called as thermal stratification of the surge pipe. Presently, the surge pipes of PWR nuclear power plants are usually arranged in a subhorizontal way (with. elevation of only 17), therefore, the pipeline radial cross-section suffers severe thermal stratification, resulting in severe thermal stress impact on the surge pipe body and key welding seams (especially the welding seam at the junction of the surge pipe and the main loop).
Thermal stratification of surge pipe has always been not only one of the factors threatening the safety of the nuclear power plant but also a key concern of the Natioi.al Nuclear Safety Administration. In Ling'ao Nuclear Power Plant Phase I, the cumulative fatigue usage factor of the surge pipe is close to the limit.
Summary of the Invention
The present invention is to provide a vertical connection type surge pipe lbr o pressurizer of pressurized, water reactor (PWR) nuclear power plant, which cart not only effectively connect the pressurizer with the main loop but also effectively alleviate the impact of thermal stratification on surge pipe and the nozzle of the main pipe.
The technical solution to achieve the present invention is as follows: is A vertical connection type surge pipe thr pressurizer of pressurized water reactor (PWR) nuclear power plant, comr rising a vertical section 1, a vertical section II and an extension section between the two, wherein the vertical section I is vertically connected outside from the top of a main loop pipeline; the vertical section II is vertically connected upwards with the bottom of a pressurizer; and the extension section extends upwards at an elevation angle of 2-5 degrees with the horizontal plane.
The vertical connection type surge pipe fbr pressurizer of pressurized water reactor (PWR) nuclear power plant. wherein the extension section is composed of a straight pipe section. a curved section I, a curved section II and a semicircuiar section; one end of the straight pipe section is vertically connected with the top of a main loop pipeline, and the other end is connected with the curved section 1; the semicircular section is located be:tween the curved section 1 and the curved section II; one end of the curved section Ii is vertically connected upwards with the bottom of the pressurizer and the other end is connected to the semicircuiar section.
The beneficial effects of the present invention are as follows: the designed vertical sections allow the surge pipe to be vertically connected outside from a main pipeline so that the thermal stratification influence on the weldin.g seam of the surge pipe nozzk of the main pipeline is avoided; and the extension section in the middle section of the surge pipe extends upwards at an elevation angle of 25 degrees so that the influence of thermal strati fleation effect on the welding seam is efiectively relieved,
Brkf Description of Drawings
Fig. 1 is the side view of the vertical cormection type surge pipe for pressurizer of pressurized water reactor (PWR) nuclear power plant.
Fig. 2 is the top view of Fig. 1, In the figures, 1 refers to the vertical section 1; 2 refers to the vertical section II; 3 refers to the extension section; 301 refers to the straight pipe section; 302 refers to the semicircuiar section; 303 refers to the curved section 1; and 304 refers to the curved section IL Ernbdiments The following drawings and specific embodiments are further Uescnption of the present invention in details.
As shown in Fig. 1, the surge pipe comprises two verlical sections, namely the vertical section ii and the vertical section 112, and further comprises the extension section 3 between the vertical section 1. and the vertical section 2, wherein the vertical section II is vertically connected outside from of the top of main loop pipeline so that there will he no thermal stratification on the crosssection of the welding seam, which can ensure the operation safety and operating life after the main pipeline is connected with this place. The other vertical section 112 is vertically connected upwards with the bottom of the pressurizer to achieve the connection of the main loop and the pressurizer.
The extension section 3 between the vertical section 1 and the vertical s section 2 extends upwards at an elevation angle of. 2.5 degrees with the horizontal plane. The inclination angle is maintained and the slope is large enough to effectively control the impact of the thermal stratification on the extension section 3 of the surge pipe.
In this embodiment, the extension section 1 is designed in an optimal form.
As shown in Fig. 2, the extension 3 consists of four parts, namely a straight pipe section 301, a curved section 1 303, a curved section II 304 and a sernicircular section 302 between the curved section 1 303 and the curved section Ii 304, T..he -i four parts fbrm a pipe section nearly in the shape of fi.
Obviously, a person skilled in the field can make various changes and modifications for the present invention, without departing from the spirit and scope of the present invention, in the case that such changes and modifications are S withii tl.ie scope of the claims of the present invention and the equivalent technical scope. the present invention is also intended to inc'ude these changes and modifications.

Claims (2)

  1. Claims 1. A vertical connection type surge pipe for pressurizer of pressurized water reactor (PWR) nuclear power plant, comprising a vertical section I (1), a verlical section 11(2) and an extension section (3) between the vertical section 1(1) and the vertical section 11(2), wherein the vertical section 1(1) is vertically connected outside from the top of the main loop pipeline, the vertical section II (2) is veiticali) con..iiected upwards with the bottom of a pressurizer; and the extension section (3) extends upwards at an elevation angle of 25 degrees with the horizontal plane.
  2. 2. The vertical connection type surge pipe:ibr pressurizer of pressurized water reactor (PWR) nuclear power plant according to Claim 1, wherein the extension section (3) is composed of a straight pipe section (301), a curved section 1 (303), a curved section H (304) and a semicircuIar section (302); one end of the straight pipe section (301) is vertically connected with the top of the main loop pipeline and the other end is connected with the curved section 1(303); the semicircuiar section (302) is located between the curved section 1(303) and the curved section 11(304); one end of the curved section 11(304) is vertically connected upwards with the bottom of the pressurizer and the other end is connected to the semicircular section (302).
GB1511704.7A 2012-12-06 2013-12-03 Vertical connection type surge pipe for pressurizer of pressurized water reactor nuclear power plant Active GB2523706B (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
CN201210519796.2A CN103854709A (en) 2012-12-06 2012-12-06 Vertical connection type surge pipe for pressurized water reactor nuclear power plant voltage stabilizer
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

Publications (3)

Publication Number Publication Date
GB201511704D0 GB201511704D0 (en) 2015-08-19
GB2523706A true GB2523706A (en) 2015-09-02
GB2523706B GB2523706B (en) 2017-12-06

Family

ID=50862256

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1511704.7A Active GB2523706B (en) 2012-12-06 2013-12-03 Vertical connection type surge pipe for pressurizer 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)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
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
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)

* Cited by examiner, † Cited by third party
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)

* Cited by examiner, † Cited by third party
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

Patent Citations (6)

* Cited by examiner, † Cited by third party
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

Also Published As

Publication number Publication date
ZA201504856B (en) 2017-04-26
WO2014086274A1 (en) 2014-06-12
GB2523706B (en) 2017-12-06
AR093808A1 (en) 2015-06-24
GB201511704D0 (en) 2015-08-19
CN103854709A (en) 2014-06-11

Similar Documents

Publication Publication Date Title
CN103377735B (en) A kind of reactor bottom in-pile component
CN104508754B (en) Core steam feed system
CN108922643A (en) A kind of small-sized heap reactor-loop overall structure of compact Layout
CN102867549B (en) Reactor cavity water injection cooling system with combination of active and passive power
CN103544997A (en) Positioning grid rack and reactor fuel assembly
GB2536990A (en) Flow distribution device and nuclear reactor assembly with same
GB2523706A (en) Vertical connection type surge pipe for voltage stabilizer of pressurized water reactor nuclear power plant
CN102637464A (en) Strengthened heat exchange method and device of double-layer concrete containment passive heat derived system
CN103310855A (en) Liquid heavy metal cooling reactor fuel assembly
CN104235594A (en) Horizontal double-layer buried storage tank
CN206849504U (en) A kind of impact-resistant reactor pressure vessel adapter segment structure
CN102208218B (en) Primary helium fan intake header for high-temperature gas-cooled reactor
CN203931516U (en) A kind of Passive containment cooling system of applying phase-change heat transfer
CN203026164U (en) Vertical connection type surge pipe for voltage stabilizer of pressurized water reactor nuclear power plant
MY184252A (en) Fast neutron reactor and neutron reflector block of a fast neutron reactor
CN102332314B (en) Water-cooling wall
CN204067839U (en) Laser is from drainage type cooled plate
JP5788958B2 (en) Imizu Dam Power Generator
CN102996908B (en) Pipeline capable of reducing influence of thermal stratification
CN202059310U (en) Cooling water pipe for power module of electric locomotive main converter
CN204029552U (en) A kind of Large Copacity Horizontal water cooling reactor
JP7416544B2 (en) Molten salt fast reactor
CN103862186A (en) Welding structure for electric heating element sleeves of pressurized water reactor nuclear power plant voltage stabilizer
CN103486084B (en) A kind of high temperature gas cooled reactor main helium fan volute structure
CN203440387U (en) Blast furnace tuyere platform capable of effectively preventing temperature-rise deformation

Legal Events

Date Code Title Description
789A Request for publication of translation (sect. 89(a)/1977)

Ref document number: 2014086274

Country of ref document: WO