WO2013186250A3 - Method for operating the steam generator of a power plant, in particular of a nuclear power plant - Google Patents

Method for operating the steam generator of a power plant, in particular of a nuclear power plant Download PDF

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Publication number
WO2013186250A3
WO2013186250A3 PCT/EP2013/062126 EP2013062126W WO2013186250A3 WO 2013186250 A3 WO2013186250 A3 WO 2013186250A3 EP 2013062126 W EP2013062126 W EP 2013062126W WO 2013186250 A3 WO2013186250 A3 WO 2013186250A3
Authority
WO
WIPO (PCT)
Prior art keywords
power plant
steam generator
pipes
operating
intensity
Prior art date
Application number
PCT/EP2013/062126
Other languages
German (de)
French (fr)
Other versions
WO2013186250A2 (en
Inventor
Peter Forster
Gerrit GLOTH
Jürgen DENNERLEIN
Iryna JANKE
Original Assignee
Areva Gmbh
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 Areva Gmbh filed Critical Areva Gmbh
Publication of WO2013186250A2 publication Critical patent/WO2013186250A2/en
Publication of WO2013186250A3 publication Critical patent/WO2013186250A3/en

Links

Classifications

    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00Methods of steam generation characterised by form of heating method
    • F22B1/02Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/023Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers with heating tubes, for nuclear reactors as far as they are not classified, according to a specified heating fluid, in another group
    • F22B1/025Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers with heating tubes, for nuclear reactors as far as they are not classified, according to a specified heating fluid, in another group with vertical U shaped tubes carried on a horizontal tube sheet
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B35/00Control systems for steam boilers
    • F22B35/004Control systems for steam generators of nuclear power plants
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B35/00Control systems for steam boilers
    • F22B35/18Applications of computers to steam boiler control
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00Component parts or details of steam boilers
    • F22B37/002Component parts or details of steam boilers specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment not otherwise provided for
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00Component parts or details of steam boilers
    • F22B37/02Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/38Determining or indicating operating conditions in steam boilers, e.g. monitoring direction or rate of water flow through water tubes
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00Component parts or details of steam boilers
    • F22B37/02Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/42Applications, arrangements, or dispositions of alarm or automatic safety devices
    • F22B37/421Arrangements for detecting leaks
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/017Inspection or maintenance of pipe-lines or tubes in nuclear installations
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Combustion & Propulsion (AREA)
  • Chemical & Material Sciences (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention relates to a method for operating a steam generator (1) of a power plant, in particular of a nuclear power plant, wherein the steam generator comprises a secondary chamber (4) and, arranged therein, a multiplicity of pipes (7) which are in the form of U-shaped pipes and which have two parallel-running legs (8) and a pipe bend (9) connecting said legs to one another. Bending oscillations of a pipe caused by a medium flowing through the secondary chamber and/or through the pipes are detected by virtue of a parameter which characterizes the intensity of the bending oscillation being detected by means of a sensor and, if a threshold range of the vibration intensity which is critical with regard to damage to the pipes is approached or reached, the operating conditions of the steam generator being set such that bending oscillations occur with an intensity that lies outside the threshold range.
PCT/EP2013/062126 2012-06-12 2013-06-12 Method for operating the steam generator of a power plant, in particular of a nuclear power plant WO2013186250A2 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE102012209855.0 2012-06-12
DE102012209855 2012-06-12

Publications (2)

Publication Number Publication Date
WO2013186250A2 WO2013186250A2 (en) 2013-12-19
WO2013186250A3 true WO2013186250A3 (en) 2014-04-10

Family

ID=48748166

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/EP2013/062126 WO2013186250A2 (en) 2012-06-12 2013-06-12 Method for operating the steam generator of a power plant, in particular of a nuclear power plant

Country Status (1)

Country Link
WO (1) WO2013186250A2 (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105066083A (en) * 2015-09-11 2015-11-18 中山大学 U-shaped-row-tube type fused salt steam generating device and method
FR3044157B1 (en) * 2015-11-24 2017-12-15 Electricite De France ANALYSIS OF A MECHANICAL STRUCTURE IN RESPONSE TO FLUID LOADING BY HYBRID TESTING

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4523466A (en) * 1983-10-31 1985-06-18 Combustion Engineering, Inc. Acoustic monitoring of tube vibration
EP0243082A2 (en) * 1986-04-18 1987-10-28 Westinghouse Electric Corporation Gap measurement eddy current probe
FR2745115A1 (en) * 1996-02-16 1997-08-22 Framatome Sa Checking housing condition of tube within steam generator of pressurised water reactor
EP2194535A1 (en) * 2007-09-25 2010-06-09 Kabushiki Kaisha Toshiba Oscillation evaluation device and evaluation method

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4523466A (en) * 1983-10-31 1985-06-18 Combustion Engineering, Inc. Acoustic monitoring of tube vibration
EP0243082A2 (en) * 1986-04-18 1987-10-28 Westinghouse Electric Corporation Gap measurement eddy current probe
FR2745115A1 (en) * 1996-02-16 1997-08-22 Framatome Sa Checking housing condition of tube within steam generator of pressurised water reactor
EP2194535A1 (en) * 2007-09-25 2010-06-09 Kabushiki Kaisha Toshiba Oscillation evaluation device and evaluation method

Also Published As

Publication number Publication date
WO2013186250A2 (en) 2013-12-19

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