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RISWelding Residual Stress in a Large Diameter Nuclear Reactor Pressure Vessel Nozzle
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The Atucha II nuclear power plant is a pressurized heavy water reactor (PHWR) being constructed in Argentina. The original plant was designed by Kraftwerk Union (KWU) in the 1970’s using the German methodology of break ...
Leak Before Break Under Beyond Design Basis Seismic Loading
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The Atucha II nuclear power plant is a unique pressurized heavy water reactor (PHWR) being constructed in Argentina. The original plant design was by Kraftwerk Union (KWU) in the 1970's using the German methodology of break ...
Assessing the Secondary Stress in a Pipe System With Circumferential Surface Crack Using Finite Element Modeling
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: In flaw evaluation criteria, the design limits for the secondary stresses are frequently different than the primary stresses. The evaluation procedure for primary stresses is load-controlled based which is independent of ...