... 11 2008 15 05 2009 design engineering nuclear engineering pipes reliability safety design LRFD nuclear piping pressure probabilistic reliability The design by rule of Class 1, 2, and 3 nuclear pipes for internal pressure in the American Society of Mechanical...

... bending nuclear engineering pipes elastoplasticity simplified elastic-plastic analysis Ke factor shakedown notch factor fatigue design-by-analysis This paper is a revision of a paper (PVP2005-71420) of the same title that was presented at the 2005 PVP conference. The design...

... ,” in Pressure Vessel and Piping: Design and Analysis, A Decade of Progress, Volume 1, Analysis , ASME , New York , pp. 209 – 226 [reprint of ASME Paper No. 68-PVP-3, 1968 ]. 26 08 2005 24 10 2005 nuclear engineering fission reactor design thermal stresses ductility design...

... power stations hydraulic systems coolant-fuel interactions heat transfer safety fission reactor safety failure (mechanical) earthquakes pressure vessels nuclear engineering In nuclear power plants, the primary heat transport system (PHTS) is designed according to ASME Section 3 Division...

... that the curvature-corrected CCP solution is a close approximation. The maximum storage tank fluid level for a postulated flaw size can be established based on the J -integral flaw stability methodology. [S0094-9930(00)00502-3] carbon steel fracture mechanics petroleum industry nuclear engineering cracks...

... No. 1389. carbon steel fracture mechanics mechanical properties deformation pipe flow elasticity plasticity pressure vessels petroleum industry nuclear engineering stress corrosion cracking 2000 ASME ...