...Ankit R. Dubey; Abhinav Gupta; Sung Gook Cho Fragility assessment requires characterization of a component or system's performance through a performance function/limit-state equation. The exceedance of limit-state is representative of failure or damage state. For the purposes of evaluating piping...

...Shaoxiang Qian; James Frith; Naoto Kasahara 1 Corresponding author. Contributed by the Pressure Vessel and Piping Division of ASME for publication in the J OURNAL OF P RESSURE V ESSEL T ECHNOLOGY . Manuscript received December 19, 2013; final manuscript received June 22, 2014...

.... To exacerbate and complicate this additional type of fatigue damage, power plant design pressures and temperatures are rising, new materials are being introduced, pipes and attached components are becoming increasingly thick, and owners are requiring power plants to heat-up and cool-down at faster rates. Also...

...Kleio Avrithi, PhD; Bilal M. Ayyub, PhD This paper presents a reliability-based low-cycle fatigue design approach for class 2 and 3 nuclear pipes. Initially, the methodology and background for the design of the pipes according to the ASME Boiler and Pressure Vessel (B&PV) Code is presented...

...Kleio Avrithi; Bilal M. Ayyub, PE Class 2 and 3 nuclear piping is designed according to the allowable stress design (ASD) method used in the ASME Boiler and Pressure Vessel (B&PV) code, Sec. III, Division 1, NC and ND-3600 according to which safety factors applied to the strength of steel...

...Kleio Avrithi; Bilal M. Ayyub Nuclear pipes are designed to withstand primary membrane stresses generated by internal pressure according to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section III, Parts NB-3641, NC-3641, and ND-3641, which uses...