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RISA Reliability-Based Expression of ASME B&PV Code Equation (11) for Class 2 and 3 Nuclear Pipes
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Previous research provided a reliability-based approach for the low-cycle fatigue design of Class 2 and 3 nuclear pipes. Reliability-based equations incorporate a threshold for the piping reliability ...
A Reliability-Based Approach for the Design of Nuclear Piping for Internal Pressure
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: 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) ...
Strength Model Uncertainties of Burst, Yielding, and Excessive Bending of Piping
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Nuclear safety-piping is designed according to the ASME Boiler and Pressure Vessel Code, Sections III, NB-, NC-, and ND-3600 that use the allowable stress design method (ASD). The potential use ...
Load and Resistance Factor Design (LRFD) of Nuclear Straight Pipes for Loads That Cause Primary Stress
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: 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 ...
A Reliability-Based Approach for Low-Cycle Fatigue Design of Class 2 and 3 Nuclear Piping
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: 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 ...