EXPERIMENTAL AND ANALYTICAL VERIFICATION OF ASME SECTION III, DIVISION 5 CREEP-FATIGUE DESIGN RULES

Yanli Wang, Robert Jetter, Ting Leung Sham

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

The continuous advancement of structural materials and the growing demands for more reliable and economical structural components in high-temperature reactor applications have necessitated the development of comprehensive design methodologies and design rules. Mechanical degradation of structural components at elevated temperatures subjected to cyclic deformation is controlled by the creep-fatigue damage. Over the past few decades, diligent research efforts have been dedicated to refining the development of elevated temperature design rules in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC), Section III, Division 5 and to develop conservative design rules that can effectively guard against the risk of creep-fatigue failure. In ASME Section III, Division 5, for a design to pass the creep-fatigue acceptance criteria, creep damage and fatigue damage are evaluated separately, and these damages must not violate the bi-linear creep-fatigue interaction diagram, i.e., the so-called D-diagram. The creep-fatigue damage evaluation procedure assumes that the effects of the actual cyclic loading sequence can be bounded by assuming that the individual loading cycles are uniformly distributed throughout the component design life. In this study, creep-fatigue experiments with variable amplitudes and loading sequencies were designed and performed on Alloy 617 at high temperatures. The results were analyzed to evaluate the loading history effect on creep-fatigue damage accumulation and to verify the assumptions for the creep-fatigue evaluation design rules.

Original languageEnglish
Title of host publicationCodes and Standards; Computer Technology and Bolted Joints
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Electronic)9780791888476
DOIs
StatePublished - 2024
EventASME 2024 Pressure Vessels and Piping Conference, PVP 2024 - Bellevue, United States
Duration: Jul 28 2024Aug 2 2024

Publication series

NameAmerican Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Volume1
ISSN (Print)0277-027X

Conference

ConferenceASME 2024 Pressure Vessels and Piping Conference, PVP 2024
Country/TerritoryUnited States
CityBellevue
Period07/28/2408/2/24

Funding

The research was sponsored by the U.S. Department of Energy, Office of Nuclear Energy, under contract No. DEAC05-00OR22725 with Oak Ridge National Laboratory (ORNL), managed and operated by UT-Battelle, LLC, and under contract No. DE-AC07-05ID14517 with Idaho National Laboratory (INL), managed and operated by Battelle Energy Alliance, LLC. Programmatic direction was provided by the Office of Nuclear Reactor Deployment of the Office of Nuclear Energy. The contribution of Brad Hall and Charles S. Hawkins of ORNL in running the experiments is greatly appreciated. The authors acknowledge Peijun Hou of Imtech Corporation, Knoxville, Tennessee for the data analysis and technical support.

FundersFunder number
U.S. Department of Energy
Idaho National Laboratory
Brad Hall and Charles S. Hawkins of ORNL
Office of Nuclear Reactor Deployment
Office of Nuclear EnergyDEAC05-00OR22725
Office of Nuclear Energy
Oak Ridge National LaboratoryDE-AC07-05ID14517
Oak Ridge National Laboratory

    Keywords

    • Creep-fatigue
    • damage summation

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