• Title of article

    Behaviour of a PWR vessel dissimilar metal weld during a steam line break transient

  • Author/Authors

    Bhandari، S. نويسنده , , Dubois، D. نويسنده , , Guichard، D. نويسنده ,

  • Issue Information
    دوهفته نامه با شماره پیاپی سال 2001
  • Pages
    -326
  • From page
    327
  • To page
    0
  • Abstract
    This paper presents the results of a Finite Element analysis conducted on the behaviour of a 15 mm deep fully circumferential crack on the outer surface of a bi-metallic weld of a 900 MWe Pressurized Water Reactor vessel, during a Steam Line Break transient. The typical weld considered connects the stainless-steel hot leg with the ferritic vessel. This work is part of a Benchmark exercise organised in the framework of an European Commission (DG Environment) project on Transition Welds. However, the results presented here concern only those obtained at Framatome using SYSTUS + code and deal with the thermo-mechanical analysis, the evaluation of the crack driving energy (J-integral) and a discussion on crack stability. These results are compared with those obtained using a simplified method developed earlier and presented at one of the international conferences.
  • Keywords
    Plant life management , Power plants , Power stations
  • Journal title
    Nuclear Engineering and Design
  • Serial Year
    2001
  • Journal title
    Nuclear Engineering and Design
  • Record number

    13697