• Title of article

    Structural integrity assessment of aging nuclear reactor pressure vessels Original Research Article

  • Author/Authors

    W.E. Pennell، نويسنده , , S.N.M. Malik، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 1997
  • Pages
    21
  • From page
    27
  • To page
    47
  • Abstract
    Irradiation embrittlement reduces both the cleavage fracture toughness and the ductile tearing toughness of reactor pressure vessel (RPV) steels. Extensive research programs have investigated the fracture behavior of heavy-section vessels containing flaws. Information obtained from that research has been used to develop regulatory guidance for evaluating the structural integrity of irradiated RPVs. Additional research programs have developed fracture analysis methods, and generated the data required for their implementation. Regulatory guidance employs fracture analysis technology to assure that adequate fracture-prevention margins for RPVs are maintained throughout the licensed operating period of nuclear power plants.
  • Journal title
    Nuclear Engineering and Design Eslah
  • Serial Year
    1997
  • Journal title
    Nuclear Engineering and Design Eslah
  • Record number

    888255