The objectives of the symposium were to provide an overview of progress in understanding materials behavior relevant to structural integrity assessments, covering mechanisms of flow and fracture, effects of neutron irradiation, reheat cracking, weld quality and inspection issues, fracture toughness characterization, crack arrest, materials behavior under dynamic loading and local approach modeling of the ductile-brittle transition
Technical
{PDF} Fracture, Plastic Flow, and Structural Integrity: Proceedings of the 7th Symposium Organized by the Technical Advisory Group in Structural Integrity of Nuclear Plant, April 1999 Staff, P.B. Hirsch, D. Lidbury
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