Evaluation of Implicit Reliability Level Associated with Fatigue Design Criteria of Nuclear Class-1 Piping

Author:

Mishra J.,Balasubramaniyan V.

Publisher

Springer Singapore

Reference13 articles.

1. American Society of Mechanical Engineers (ASME), Rules for construction of nuclear facility components, ASME Boiler & Pressure Vessel Code (2010)

2. Gupta A, Choi B (2003) Reliability-based load and resistance factor design for piping: an exploratory case study. Nucl Eng Des 224:161–178

3. Hill III RS (2004) Probabilistic & system—based methods for design—development of reliability-based load and resistance factor design methods for piping. ASME Nuclear Codes and Standards Workshop, New Orleans, LA

4. Chopra OK (2002) Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments, NUREG/CR-6787

5. American Society of Mechanical Engineers, Rules for construction of nuclear facility components. ASME Boiler and Pressure Vessel Code, Section-III, Appendix-I (2010)

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