RMS fatigue curves for random vibrations
Conference
·
· Am. Soc. Mech. Eng., (Pap.); (United States)
OSTI ID:6150147
Fatigue usage factors for deterministic or constant amplitude vibration stresses may be calculated with well known procedures and fatigue curves given in the ASME Boiler and Pressure Vessel Code. However, some phenomena produce nondeterministic cyclic stresses which can only be described and analyzed with statistical concepts and methods. Such stresses may be caused by turbulent fluid flow over a structure. Previous methods for solving this statistical fatigue problem are often difficult to use and may yield inaccurate results. Two such methods examined herein are Crandall's method and the ''3sigma'' method. The objective of this paper is to provide a method for creating ''RMS fatigue curves'' which accurately incorporate the requisite statistical information. These curves are given and may be used by analysts with the same ease and in the same manner as the ASME fatigue curves.
- Research Organization:
- Babcock and Wilcox, Lynchburg, Virginia
- OSTI ID:
- 6150147
- Report Number(s):
- CONF-840647-
- Conference Information:
- Journal Name: Am. Soc. Mech. Eng., (Pap.); (United States) Journal Volume: 84-PVP-60
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fatigue design curves for 6061-T6 aluminum
Fatigue Design Curves for 6061-T6 Aluminum
Fatigue design curves for 6061-T6 aluminum
Journal Article
·
Thu May 01 00:00:00 EDT 1997
· Journal of Pressure Vessel Technology
·
OSTI ID:477462
Fatigue Design Curves for 6061-T6 Aluminum
Conference
·
Wed Apr 21 00:00:00 EDT 1993
·
OSTI ID:10157028
Fatigue design curves for 6061-T6 aluminum
Conference
·
Thu Dec 31 23:00:00 EST 1992
·
OSTI ID:6584069
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
AMPLITUDES
DIAGRAMS
FATIGUE
FLUID FLOW
MATHEMATICS
MECHANICAL PROPERTIES
MECHANICAL VIBRATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
REACTOR COMPONENTS
STATISTICS
STRESSES
THERMAL POWER PLANTS
TURBULENT FLOW
220200* -- Nuclear Reactor Technology-- Components & Accessories
AMPLITUDES
DIAGRAMS
FATIGUE
FLUID FLOW
MATHEMATICS
MECHANICAL PROPERTIES
MECHANICAL VIBRATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
REACTOR COMPONENTS
STATISTICS
STRESSES
THERMAL POWER PLANTS
TURBULENT FLOW