ES466709A1 - Sistema de control de agua de alimentacion para central de energia nuclear - Google Patents

Sistema de control de agua de alimentacion para central de energia nuclear

Info

Publication number
ES466709A1
ES466709A1 ES466709A ES466709A ES466709A1 ES 466709 A1 ES466709 A1 ES 466709A1 ES 466709 A ES466709 A ES 466709A ES 466709 A ES466709 A ES 466709A ES 466709 A1 ES466709 A1 ES 466709A1
Authority
ES
Spain
Prior art keywords
nuclear
power
component
nuclear reactor
power generation
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
Application number
ES466709A
Other languages
English (en)
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
Publication of ES466709A1 publication Critical patent/ES466709A1/es
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/08—Regulation of any parameters in the plant
    • G21D3/10—Regulation of any parameters in the plant by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B35/00—Control systems for steam boilers
    • F22B35/004—Control systems for steam generators of nuclear power plants
    • 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
    • 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Combustion & Propulsion (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Control Of Turbines (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Control Of Non-Electrical Variables (AREA)

Abstract

Sistema de control de agua de alimentación para central de energía nuclear que incluye un reactor nuclear, una turbina destinada a ser accionada a partir de dicho reactor, un generador de vapor conectado con dicho reactor para obtener energía a partir del mismo, un dispositivo de circulación de fluido conectado con dicha turbina y dicho generador, incluyendo dicho dispositivo de circulación de fluido un primer ramal para hacer circular vapor desde dicho generador hasta dicha turbina con el fin de energizar dicha turbina, y un segundo ramal para hacer circular agua de alimentación desde dicha turbina hasta dicho generador, estando dicha agua de alimentación destinada a ser transformada en vapor por dicho generador utilizando la energía suministrada por dicho reactor a dicho generador, incluyendo dicho sistema de control de agua de alimentación un dispositivo de válvula montado en dicho segundo ramal para controlar la circulación de dicha agua de alimentación hasta dicho generador caracterizado porque comprende un dispositivo que responde a la magnitud de la potencia suministrado por dicho reactor y al nivel del agua en dicho generador con cargas reducidas con el fin de controlar dicho dispositivo de válvula.
ES466709A 1977-02-07 1978-02-06 Sistema de control de agua de alimentacion para central de energia nuclear Expired ES466709A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US05/766,477 US4104117A (en) 1977-02-07 1977-02-07 Nuclear reactor power generation

Publications (1)

Publication Number Publication Date
ES466709A1 true ES466709A1 (es) 1979-08-01

Family

ID=25076541

Family Applications (1)

Application Number Title Priority Date Filing Date
ES466709A Expired ES466709A1 (es) 1977-02-07 1978-02-06 Sistema de control de agua de alimentacion para central de energia nuclear

Country Status (13)

Country Link
US (1) US4104117A (es)
JP (1) JPS5830560B2 (es)
BE (1) BE863739A (es)
CA (1) CA1076371A (es)
CH (1) CH633124A5 (es)
DE (1) DE2803000A1 (es)
EG (1) EG13087A (es)
ES (1) ES466709A1 (es)
FR (1) FR2379887A1 (es)
IL (1) IL53822A (es)
IT (1) IT1093648B (es)
SE (1) SE426756B (es)
YU (1) YU41582B (es)

Families Citing this family (32)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4290850A (en) * 1978-09-01 1981-09-22 Hitachi, Ltd. Method and apparatus for controlling feedwater flow to steam generating device
JPS5552998A (en) * 1978-10-16 1980-04-17 Hitachi Ltd Reactor recirculation flow rate control device
US4302288A (en) * 1978-10-23 1981-11-24 General Electric Company Fluid level control system
JPS5651695A (en) * 1979-10-03 1981-05-09 Hitachi Ltd Nuclear reactor power control method
US4336105A (en) * 1979-12-05 1982-06-22 Westinghouse Electric Corp. Nuclear power plant steam system
JPS5726794A (en) * 1980-07-25 1982-02-12 Hitachi Ltd Load control system of atomic power plant
US4424186A (en) * 1981-03-02 1984-01-03 Westinghouse Electric Corp. Power generation
US4470948A (en) * 1981-11-04 1984-09-11 Westinghouse Electric Corp. Suppression of malfunction under water-solid conditions
US4478783A (en) * 1981-12-07 1984-10-23 The Babcock & Wilcox Company Nuclear power plant feedwater controller design
US4582672A (en) * 1982-08-11 1986-04-15 Westinghouse Electric Corp. Method and apparatus for preventing inadvertent criticality in a nuclear fueled electric powering generating unit
DE3248029C2 (de) * 1982-12-24 1987-04-09 Brown Boveri Reaktor GmbH, 6800 Mannheim Verfahren zur Verhinderung von Folgeschäden bei Leckagen, die innerhalb eines Dampferzeugers einer Druckwasserreaktoranlage zwischen Primär- und Sekundärkreislauf auftreten
US4647425A (en) * 1984-01-30 1987-03-03 Westinghouse Electric Corp. Method of vacuum degassing and refilling a reactor coolant system
US4692297A (en) * 1985-01-16 1987-09-08 Westinghouse Electric Corp. Control of nuclear reactor power plant on occurrence of rupture in coolant tubes
US4777009A (en) * 1986-06-30 1988-10-11 Combustion Engineering, Inc. Automatic steam generator feedwater control over full power range
US4738818A (en) * 1986-09-29 1988-04-19 Westinghouse Electric Corp. Feedwater control in a PWR following reactor trip
US4832898A (en) * 1987-11-25 1989-05-23 Westinghouse Electric Corp. Variable delay reactor protection system
US4912732A (en) * 1988-04-14 1990-03-27 Combustion Engineering, Inc. Automatic steam generator control at low power
US5045272A (en) * 1990-02-16 1991-09-03 Westinghouse Electric Corp. Fluid temperature balancing system
US6327323B1 (en) 1998-04-17 2001-12-04 Westinghouse Electric Company Llc Multiple reactor containment building
US6021169A (en) * 1998-10-22 2000-02-01 Abb Combustion Engineering Nuclear Power, Inc. Feedwater control over full power range for pressurized water reactor steam generators
SE532185C2 (sv) * 2007-04-10 2009-11-10 Westinghouse Electric Sweden Förfarande för att driva en reaktor hos en kärnanläggning
CN101840742B (zh) * 2010-03-29 2012-08-29 中广核工程有限公司 一种核电站数字化控制系统缺省值的设置方法及系统
EP2661753B1 (en) * 2010-12-30 2020-12-23 Kepco Engineering & Construction Company, Inc. System of controlling steam generator level during main feed-water control valve transfer for nuclear power plant
JP5964029B2 (ja) * 2011-10-26 2016-08-03 三菱重工業株式会社 蒸気発生器の補助給水弁制御装置
US8945365B2 (en) 2012-07-13 2015-02-03 Ppg Industries Ohio, Inc. Electrodepositable coating compositions exhibiting resistance to cratering
CN103050161B (zh) * 2012-12-11 2016-03-30 中国核电工程有限公司 辅助给水管线自动隔离的方法
KR101481155B1 (ko) * 2012-12-26 2015-01-09 한국전력기술 주식회사 원전 증기발생기의 수위 변화율에 따른 이득 조절장치 및 방법
EP2757123A3 (en) 2013-01-18 2017-11-01 PPG Industries Ohio Inc. Clear electrodepositable primers for radiator coatings
JP6553847B2 (ja) * 2014-06-04 2019-07-31 三菱重工業株式会社 給水制御装置および給水装置
US10961403B2 (en) 2016-07-26 2021-03-30 Ppg Industries Ohio, Inc. Electrodepositable coating compositions containing 1,1-di-activated vinyl compounds
EP3728486A1 (en) 2017-12-20 2020-10-28 PPG Industries Ohio, Inc. Electrodepositable coating compositions and electrically conductive coatings resulting therefrom
CN114242284B (zh) * 2021-12-17 2024-05-28 中国核动力研究设计院 一种核反应堆热工水力试验系统及调控方法

Family Cites Families (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1247503B (de) * 1962-09-10 1967-08-17 Sulzer Ag Verfahren zur Regelung einer Kernreaktoranlage und Kernreaktoranlage zur Ausuebung des Verfahrens
NL299322A (es) * 1963-09-13
NL128783C (es) * 1963-10-30
US3719557A (en) * 1969-05-21 1973-03-06 Sulzer Ag Circulating system for a nuclear reactor
US3638018A (en) * 1969-07-14 1972-01-25 Mc Donnell Douglas Corp Means of measuring temperature and neutron flux
BE758888A (fr) * 1969-11-18 1971-05-13 Westinghouse Electric Corp Systeme de reactivation d'une boucle de reacteur nucleaire
US3752735A (en) * 1970-07-16 1973-08-14 Combustion Eng Instrumentation for nuclear reactor core power measurements
US3791922A (en) * 1970-11-23 1974-02-12 Combustion Eng Thermal margin protection system for a nuclear reactor
US3778347A (en) * 1971-09-27 1973-12-11 Giras T Method and system for operating a boiling water reactor-steam turbine plant preferably under digital computer control
US3894912A (en) * 1972-06-21 1975-07-15 Us Energy Determination of parameters of a nuclear reactor through noise measurements
GB1445719A (en) * 1973-06-08 1976-08-11 Nuclear Power Co Whetstone Ltd Nuclear reactors
JPS5243996B2 (es) * 1973-10-24 1977-11-04
US4000037A (en) * 1973-11-28 1976-12-28 Westinghouse Electric Corporation Reactor-turbine control for low steam pressure operation in a pressurized water reactor
US3973402A (en) * 1974-01-29 1976-08-10 Westinghouse Electric Corporation Cycle improvement for nuclear steam power plant
JPS51104191A (es) * 1975-03-10 1976-09-14 Hitachi Ltd
BE829567A (fr) * 1975-05-28 1975-11-28 Acec Installation de reglage d'admission d'eau alimentaire secondaire au bas d'un generateur de vapeur

Also Published As

Publication number Publication date
FR2379887A1 (fr) 1978-09-01
EG13087A (en) 1980-10-31
IT1093648B (it) 1985-07-19
IT7820048A0 (it) 1978-02-07
IL53822A (en) 1982-01-31
SE426756B (sv) 1983-02-07
BE863739A (fr) 1978-08-07
JPS53102495A (en) 1978-09-06
CA1076371A (en) 1980-04-29
YU19678A (en) 1982-08-31
CH633124A5 (de) 1982-11-15
JPS5830560B2 (ja) 1983-06-29
FR2379887B1 (es) 1981-06-26
YU41582B (en) 1987-10-31
US4104117A (en) 1978-08-01
DE2803000A1 (de) 1978-08-10
SE7801365L (sv) 1978-08-08

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Legal Events

Date Code Title Description
FD1A Patent lapsed

Effective date: 20000301