Report No. 3: Technical basis for a revised fatigue crack growth rate curve for ferritic steels in light water reactor environments

Journal Article · Tue Aug 01 00:00:00 EDT 1995 · Bulletin - Welding Research Council

OSTI ID:197649

Eason, E D; Nelson, E E ^[1]; Gilman, J D ^[2]

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1. Modeling and Computing Services, Boulder, CO (United States)
2. Electric Power Research Inst., Palo Alto, CA (United States)

This paper presents the technical basis for improved fatigue crack propagation reference curves for pressure vessel and related ferritic steels in light water reactor (LWR) environments. The primary improvements over previous reference curves are explicit modeling of load rise time effects, calibration to a much larger set of data analyzed in a consistent manner, and adjustment of the reference curves to be conservative over the range of reactor operating temperatures. The reference curves are proposed for inclusion in the non-mandatory Appendix A of the ASME Pressure Vessel Code, Section 11. Important variables that are not explicitly included in the reference curves are discussed.

• OSTI ID: 197649
• Journal Information: Bulletin - Welding Research Council, Journal Issue: 404; Other Information: PBD: Aug 1995
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
WATER COOLED REACTORS
REACTOR MATERIALS
FERRITIC STEELS
FATIGUE
CRACK PROPAGATION
MATHEMATICAL MODELS
STANDARDS
TEMPERATURE DEPENDENCE