ES432355A1 - Metodo para prolongar el funcionamiento de una instalacion generadora de vapor por energia nuclear. - Google Patents

Metodo para prolongar el funcionamiento de una instalacion generadora de vapor por energia nuclear.

Info

Publication number
ES432355A1
ES432355A1 ES432355A ES432355A ES432355A1 ES 432355 A1 ES432355 A1 ES 432355A1 ES 432355 A ES432355 A ES 432355A ES 432355 A ES432355 A ES 432355A ES 432355 A1 ES432355 A1 ES 432355A1
Authority
ES
Spain
Prior art keywords
reactor
steam
control system
flow interruption
interruption means
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
ES432355A
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 ES432355A1 publication Critical patent/ES432355A1/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
    • G21D3/12—Regulation of any parameters in the plant by adjustment of the reactor in response only to changes in engine demand
    • G21D3/16—Varying reactivity
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/32—Control of nuclear reaction by varying flow of coolant through the core by adjusting the coolant or moderator temperature
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Control Of Turbines (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Engine Equipment That Uses Special Cycles (AREA)
ES432355A 1973-11-28 1974-11-27 Metodo para prolongar el funcionamiento de una instalacion generadora de vapor por energia nuclear. Expired ES432355A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US05/419,746 US4000037A (en) 1973-11-28 1973-11-28 Reactor-turbine control for low steam pressure operation in a pressurized water reactor

Publications (1)

Publication Number Publication Date
ES432355A1 true ES432355A1 (es) 1977-06-16

Family

ID=23663578

Family Applications (1)

Application Number Title Priority Date Filing Date
ES432355A Expired ES432355A1 (es) 1973-11-28 1974-11-27 Metodo para prolongar el funcionamiento de una instalacion generadora de vapor por energia nuclear.

Country Status (12)

Country Link
US (1) US4000037A (es)
JP (1) JPS5531920B2 (es)
BE (1) BE822679A (es)
CA (1) CA1022352A (es)
CH (1) CH587539A5 (es)
DE (1) DE2452151A1 (es)
ES (1) ES432355A1 (es)
FR (1) FR2252632B1 (es)
GB (1) GB1456297A (es)
IT (1) IT1026519B (es)
NL (1) NL7414168A (es)
SE (1) SE417259B (es)

Families Citing this family (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4263654A (en) * 1976-09-28 1981-04-21 Hitachi, Ltd. System for determining the normal operating value of power plant data
US4222822A (en) * 1977-01-19 1980-09-16 Westinghouse Electric Corp. Method for operating a nuclear reactor to accommodate load follow while maintaining a substantially constant axial power distribution
US4104117A (en) * 1977-02-07 1978-08-01 Westinghouse Electric Corp. Nuclear reactor power generation
US4290850A (en) * 1978-09-01 1981-09-22 Hitachi, Ltd. Method and apparatus for controlling feedwater flow to steam generating device
US4336105A (en) * 1979-12-05 1982-06-22 Westinghouse Electric Corp. Nuclear power plant steam system
JPH01168689U (es) * 1988-05-20 1989-11-28
US5215704A (en) * 1991-06-24 1993-06-01 Electric Power Research Institute Method and apparatus for in situ testing of heat exchangers
US9316122B2 (en) 2010-12-20 2016-04-19 Invensys Systems, Inc. Feedwater heater control system for improved Rankine cycle power plant efficiency
US9091182B2 (en) * 2010-12-20 2015-07-28 Invensys Systems, Inc. Feedwater heater control system for improved rankine cycle power plant efficiency
US9297278B2 (en) * 2011-05-27 2016-03-29 General Electric Company Variable feedwater heater cycle
US9328633B2 (en) 2012-06-04 2016-05-03 General Electric Company Control of steam temperature in combined cycle power plant
FR3008220B1 (fr) * 2013-07-04 2015-08-14 Areva Np Procede de pilotage en prolongation de cycle d'un reacteur nucleaire a eau pressurisee
RU2680380C1 (ru) * 2017-12-01 2019-02-20 Рашид Зарифович Аминов Способ повышения мощности и безопасности энергоблока АЭС с реактором типа ВВЭР на основе теплового аккумулирования

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3061533A (en) * 1958-05-12 1962-10-30 United Eng & Constructors Inc Control means for a boiling water nuclear reactor power system
NL291393A (es) * 1963-03-20
CH405517A (de) * 1963-05-17 1966-01-15 Sulzer Ag Verfahren und Vorrichtung zur Regelung einer Reaktoranlage
US3197380A (en) * 1964-09-16 1965-07-27 Dahlgren Jons Arthur Power plant for superheating the steam originating from the steam generator of a nuclear pressurized water reactor
FR1527695A (fr) * 1966-02-03 1968-06-07 Stein & Roubaix S A Installation thermique
US3660229A (en) * 1969-02-07 1972-05-02 Gen Electric Canada Reactor control system
BE758888A (fr) * 1969-11-18 1971-05-13 Westinghouse Electric Corp Systeme de reactivation d'une boucle de reacteur nucleaire
US3700552A (en) * 1969-11-19 1972-10-24 Babcock & Wilcox Co Nuclear reactor with means for adjusting coolant temperature
BE767821R (fr) * 1971-06-02 1971-10-18 Sulzer Ag Centrale nucleaire a cuve sous
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

Also Published As

Publication number Publication date
JPS5531920B2 (es) 1980-08-21
US4000037A (en) 1976-12-28
SE417259B (sv) 1981-03-02
FR2252632B1 (es) 1977-11-04
NL7414168A (nl) 1975-05-30
BE822679A (fr) 1975-05-27
CH587539A5 (es) 1977-05-13
IT1026519B (it) 1978-10-20
GB1456297A (en) 1976-11-24
JPS5084731A (es) 1975-07-08
FR2252632A1 (es) 1975-06-20
CA1022352A (en) 1977-12-13
DE2452151A1 (de) 1975-06-05

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Legal Events

Date Code Title Description
FD1A Patent lapsed

Effective date: 19980202