Standardized method for developing stress intensification factors for piping components

Journal Article · Wed Jun 01 00:00:00 EDT 1994 · Welding Research Council Bulletin; (United States)

OSTI ID:6929802

Rodabaugh, E C ^[1]

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1. Rodabaugh (E.C.), Dublin, OH (United States)

At present, neither the ASME Boiler and Pressure Vessel Code for Nuclear Power Plant Components (ASME B PV Code Section 3) nor the B31 codes for industrial piping provide a methodology for experimental determination of i-factors. This report examines the basis for the present Code fatigue rules and how the original i-factors were determined. It then provides a set of proposed additions to the code, Appendix 2, to guide users in developing i-factors. Such an appendix, with minor modification, can also be used by the B31 industrial piping codes.

• OSTI ID: 6929802
• Journal Information: Welding Research Council Bulletin; (United States), Journal Name: Welding Research Council Bulletin; (United States) Vol. 392; ISSN 0421-2118; ISSN WRCBB3
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420200* -- Engineering-- Facilities
Equipment
& Techniques
FAILURES
MATERIALS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
STANDARDS
STRESS INTENSITY FACTORS
THERMAL POWER PLANTS