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  • International Association for Structural Mechanics in Reactor Technology (IASMiRT)
  • 1975 - SMiRT 3 - London, UK
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    F - Structural Analysis of Reactor Core and Coolant Circuit Structures [69]
    F1 - Dynamic Analysis of Reactor Core Structures [10]
    F2 - Solid-Fluid Interaction Phenomena [11]
    F3 - Structural Analysis of Pipework Systems [9]
    F4 - Dynamic Analysis of Pipework Systems I [8]
    F5 - Dynamic Analysis of Pipework Systems II [6]
    F6 - Structural Analysis of Diverse Coolant Circuit Components [8]
    F7 - Structural Analysis of Heat Exchangers [10]
    F8 - Miscellaneous Topics [7]
    G - Structural Analysis of Steel Reactor Pressure Vessels [36]
    G1 - Stress and Strain Analysis of Reactor Pressure Vessels [8]
    G2 - Analysis of Pressure Vessel Heads [7]
    G3 - Assessment of the Integrity and Reliability of Reactor Pressure Vessels [9]
    G4 - Fracture Mechanics Analysis I [7]
    G5 - Fracture Mechanics Analysis II [5]
    H - Structural Analysis of Prestressed Concrete Reactor Pressure Vessels [38]
    H1 - Concrete Properties Relevant to PCRV [10]
    H2 - Structural Analysis I [9]
    H3 - Structural Analysis II [10]
    H4 - Failure Mode Analysis [9]

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