ES2050942T3 - Sistema de reactor nuclear de agua a presion con mitigador de vortice en rama caliente. - Google Patents

Sistema de reactor nuclear de agua a presion con mitigador de vortice en rama caliente.

Info

Publication number
ES2050942T3
ES2050942T3 ES90300028T ES90300028T ES2050942T3 ES 2050942 T3 ES2050942 T3 ES 2050942T3 ES 90300028 T ES90300028 T ES 90300028T ES 90300028 T ES90300028 T ES 90300028T ES 2050942 T3 ES2050942 T3 ES 2050942T3
Authority
ES
Spain
Prior art keywords
mitigator
hot
reactor system
vortice
rama
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.)
Expired - Lifetime
Application number
ES90300028T
Other languages
English (en)
Inventor
Louis Kowk-Shuen Lau
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.)
CBS Corp
Original Assignee
Westinghouse Electric Corp
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 Westinghouse Electric Corp filed Critical Westinghouse Electric Corp
Application granted granted Critical
Publication of ES2050942T3 publication Critical patent/ES2050942T3/es
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G21C1/086—Pressurised water reactors
    • 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
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
    • G21C15/187—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps using energy from the electric grid
    • 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)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Structures Of Non-Positive Displacement Pumps (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Jet Pumps And Other Pumps (AREA)

Abstract

UN SISTEMA DE REACTOR NUCLEAR DE AGUA PRESURIZADA (1) INCLUYE UN MITIGADOR VORTEX EN FORMA DE UNA CONDUCCION CILINDRICA (33) ENTRE EL CONDUCTO DE LA RAMA CALIENTE (11) Y UNA PRIMERA SECCION (21) DE CONDUCTO DE ELIMINACION DEL CALOR RESIDUAL, CUYO CONDUCTO (21) LLEVA HASTA UNA BOMBA (23) Y UNA SEGUNDA SECCION (25) DE CONDUCTO DE ELIMINACION DE CALOR RESIDUAL QUE VUELVE A LA VASIJA DE PRESION DEL REACTOR (3). EL CONDUCTO CILINDRICO (33) ES DE TAMAÑO TAL QUE, DONDE LA RAMA CALIENTE (11) TIENE UN DIAMETRO INTERNO D1, LA PRIMERA SECCION (21 TIENE UN DIAMETRO INTERNO D2, Y EL CONDUCTO CILINDRICO (33) O LA BOQUILLA DE PASO TIENE UNA LONGITUD L Y UN DIAMETRO INTERNO DE D3; D3/D1 ES AL MENOS 0,55, D3/D2 ES AL MENOS 1,9, Y L/D3 ES AL MENOS 1,44, POR LO QUE SE IMPIDE LA CAVITACION DE LA BOMBA (23) MEDIANTE UN VORTEX FORMADO EN LA RAMA CALIENTE (11).
ES90300028T 1989-01-03 1990-01-03 Sistema de reactor nuclear de agua a presion con mitigador de vortice en rama caliente. Expired - Lifetime ES2050942T3 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US07/293,160 US4957693A (en) 1989-01-03 1989-01-03 Pressurized water nuclear reactor system with hot leg vortex mitigator

Publications (1)

Publication Number Publication Date
ES2050942T3 true ES2050942T3 (es) 1994-06-01

Family

ID=23127910

Family Applications (1)

Application Number Title Priority Date Filing Date
ES90300028T Expired - Lifetime ES2050942T3 (es) 1989-01-03 1990-01-03 Sistema de reactor nuclear de agua a presion con mitigador de vortice en rama caliente.

Country Status (5)

Country Link
US (1) US4957693A (es)
EP (1) EP0377494B1 (es)
JP (1) JP2839922B2 (es)
KR (1) KR0147358B1 (es)
ES (1) ES2050942T3 (es)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5263067A (en) * 1992-06-24 1993-11-16 Westinghouse Electric Corp. Locating hot and cold-legs in a nuclear powered steam generation system
KR0121554B1 (ko) * 1993-11-29 1997-11-22 임용규 원자력발전소 부분충수 장치와 그 운전방법
FR2718879B1 (fr) * 1994-04-13 1996-07-19 Framatome Sa Procédé de refroidissement du cÓoeur d'un réacteur nucléaire à eau sous pression pendant un arrêt à froid et circuit primaire pour la mise en Óoeuvre du procédé de refroidissement.
CN101839467B (zh) * 2010-05-10 2012-05-16 中国核电工程有限公司 一种压水堆核电站蒸汽发生器、主管道和主回路安装方法
CN102169736B (zh) * 2011-01-19 2013-01-23 中国核工业第五建设有限公司 一种核电站冷却剂系统主管道的安装方法
CN106098115A (zh) * 2016-08-11 2016-11-09 上海核工程研究设计院 一种非能动压水堆核电站反应堆冷却剂环路布置
CN109192336A (zh) * 2018-07-20 2019-01-11 中广核研究院有限公司 一种短管连接的紧凑型小型堆一回路主设备结构

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3525669A (en) * 1968-10-02 1970-08-25 Atomic Energy Commission Insulated ducts for nuclear reactors
US4064001A (en) * 1975-05-01 1977-12-20 Combustion Engineering, Inc. Hot leg relief system
UST945008I4 (es) * 1975-06-10 1976-04-06
US4187147A (en) * 1976-02-20 1980-02-05 Westinghouse Electric Corp. Recirculation system for nuclear reactors
US4280796A (en) * 1976-05-10 1981-07-28 Reinsch Arnold O W Flash jet coolant circulation system
FR2469779A1 (fr) * 1979-11-16 1981-05-22 Commissariat Energie Atomique Dispositif de refroidissement de secours du coeur d'un reacteur a eau pressurisee
FR2515853A1 (fr) * 1981-11-05 1983-05-06 Framatome Sa Dispositif de refroidissement du circuit primaire d'un reacteur nucleaire a eau sous pression
DE3417198A1 (de) * 1984-05-09 1985-11-14 Kraftwerk Union AG, 4330 Mülheim Fluessigkeitsgekuehlter-kernreaktor
US4769209A (en) * 1986-01-10 1988-09-06 Westinghouse Electric Corp. Compact small pressurized water nuclear power plant
US4753771A (en) * 1986-02-07 1988-06-28 Westinghouse Electric Corp. Passive safety system for a pressurized water nuclear reactor

Also Published As

Publication number Publication date
US4957693A (en) 1990-09-18
JP2839922B2 (ja) 1998-12-24
EP0377494A1 (en) 1990-07-11
EP0377494B1 (en) 1994-03-30
KR0147358B1 (ko) 1998-10-01
KR900012287A (ko) 1990-08-03
JPH02226096A (ja) 1990-09-07

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