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  • International Association for Structural Mechanics in Reactor Technology (IASMiRT)
  • 2007 - SMiRT 19 - Toronto, Canada
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    F - Design Methods and Rules for Components [22]
    F01 - Applicability of Current Design Standards to Current NPP Design and Review [5]
    F02 - Design Issues for Special Components [6]
    F03 - Applicability Of Current Design Standards to the Design of New Generation Reactors [4]
    F04 - Fatigue, Thermal Fatigue and Fracture Mechanics [4]
    F05 - Managing the Design Experience [3]
    G - Fracture Mechanics and Structural Integrity [40]
    G01 - Components - Reactor Pressure Vessels - I [5]
    G02 - [4]
    G03 - [6]
    G04 - [6]
    G05 - Degradation Mechanisms - Fatigue [6]
    G06 - On the Use of Finite Element Analysis [5]
    G07 - Flaw Models - I [4]
    G08 - Flaw Models - II [4]
    H - Concrete Material, Containment and Other Structures [47]
    H01 - Design Features of Concrete Containments [5]
    H02 - Aging and Degradation of Concrete Structures [5]
    H03 - Environmental and Time-Dependant Effects on Concrete Structures [6]
    H04 - Analysis of Concrete Containment and Other Structures [6]

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