AR093808A1 - VERTICAL PUMPING LINE FOR CONNECTION OF STABILIZER IN A REACTOR OF THE TYPE OF PRESSURIZED WATER - Google Patents

VERTICAL PUMPING LINE FOR CONNECTION OF STABILIZER IN A REACTOR OF THE TYPE OF PRESSURIZED WATER

Info

Publication number
AR093808A1
AR093808A1 ARP130104508A ARP130104508A AR093808A1 AR 093808 A1 AR093808 A1 AR 093808A1 AR P130104508 A ARP130104508 A AR P130104508A AR P130104508 A ARP130104508 A AR P130104508A AR 093808 A1 AR093808 A1 AR 093808A1
Authority
AR
Argentina
Prior art keywords
pumping line
stabilizer
section
vertical
reactor
Prior art date
Application number
ARP130104508A
Other languages
Spanish (es)
Inventor
Liu Xianghong
Wang Baoping
Lai Jianyong
Ren Yun
Sui Haiming
Su Rongfu
Huang Wei
Original Assignee
Nuclear Power Inst 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 Inst China filed Critical Nuclear Power Inst China
Publication of AR093808A1 publication Critical patent/AR093808A1/en

Links

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

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

Pertenece al ámbito de la tecnología nuclear, en particular se refiere a una línea de bombeo para estabilizador, la cual consta de dos secciones verticales y la sección de extensión (3) entre ambas. Una de las secciones verticales (1) conduce refrigerante desde la parte superior de la tubería de circuito principal directamente y la segunda sección vertical (2) se vincula a la parte inferior del estabilizador. La sección de extensión se extiende hacia arriba en un ángulo de elevación 2º a 5º con el plano horizontal. El diseño vertical de la primera sección hace que la línea de bombeo conduzca verticalmente desde la tubería principal, eliminando la influencia de la estratificación térmica sobre la línea de bombeo y la boca de su tubería principal. El diseño hacia arriba en ángulo de elevación de 2º a 5º de la sección de extensión en medio de la línea de bombeo alivia los efectos de estratificación térmica sobre esta sección de soldadura efectivamente.It belongs to the field of nuclear technology, in particular it refers to a stabilizer pumping line, which consists of two vertical sections and the extension section (3) between them. One of the vertical sections (1) conducts refrigerant from the top of the main circuit pipe directly and the second vertical section (2) is linked to the bottom of the stabilizer. The extension section extends upward at a 2º to 5º elevation angle with the horizontal plane. The vertical design of the first section causes the pumping line to drive vertically from the main pipe, eliminating the influence of thermal stratification on the pumping line and the mouth of its main pipe. The upward design at an elevation angle of 2º to 5º of the extension section in the middle of the pumping line relieves the effects of thermal stratification on this welding section effectively.

ARP130104508A 2012-12-06 2013-12-05 VERTICAL PUMPING LINE FOR CONNECTION OF STABILIZER IN A REACTOR OF THE TYPE OF PRESSURIZED WATER AR093808A1 (en)

Applications Claiming Priority (1)

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

Publications (1)

Publication Number Publication Date
AR093808A1 true AR093808A1 (en) 2015-06-24

Family

ID=50862256

Family Applications (1)

Application Number Title Priority Date Filing Date
ARP130104508A AR093808A1 (en) 2012-12-06 2013-12-05 VERTICAL PUMPING LINE FOR CONNECTION OF STABILIZER IN A REACTOR OF THE TYPE OF PRESSURIZED WATER

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

Family Cites Families (9)

* 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
KR101040337B1 (en) * 2008-12-01 2011-06-10 기아자동차주식회사 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
CN102760500B (en) * 2012-07-02 2015-08-05 西安交通大学 A kind of surge wave pipe structure of nuclear power station voltage stabilizer
CN102996908B (en) * 2012-11-12 2015-01-21 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
GB2523706B (en) 2017-12-06
GB201511704D0 (en) 2015-08-19
GB2523706A (en) 2015-09-02
WO2014086274A1 (en) 2014-06-12
CN103854709A (en) 2014-06-11

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