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  1. 1
    Technical Basis Part 2 for Code Case N-889: Reference Stress Corrosion Crack Growth Rate Curves for Irradiated Austenitic Stainless Steels in Light Water Reactor Environments

    Technical Basis Part 2 for Code Case N-889: Reference Stress Corrosion Crack Growth Rate Curves for Irradiated Austenitic Stainless Steels in Light Water Reactor Environments von Eason, Ernest D, Pathania, Raj, Jenssen, Anders, Weakland, Dennis P


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  2. 2
    Application of Master Curve fracture toughness for reactor pressure vessel integrity assessment in the USA

    Application of Master Curve fracture toughness for reactor pressure vessel integrity assessment in the USA von Server, William, Rosinski, Stan, Lott, Randy, Kim, Charles, Weakland, Dennis


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  3. 3
    Application of Master Curve fracture toughness for reactor pressure vessel integrity assessment in the USA : Irradiation effect in reactor pressure vessel steels

    Application of Master Curve fracture toughness for reactor pressure vessel integrity assessment in the USA : Irradiation effect in reactor pressure vessel steels von SERVER, William, ROSINSKI, Stan, LOTT, Randy, KIM, Charles, WEAKLAND, Dennis


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