NOTCH EFFECT ON CREEP-FATIGUE BEHAVIOR OF ALLOY 617 AT ELEVATED TEMPERATURE

Peijun Hou; Yanli Wang; Ting Leung Sham

doi:10.1115/PVP2023-106503

NOTCH EFFECT ON CREEP-FATIGUE BEHAVIOR OF ALLOY 617 AT ELEVATED TEMPERATURE

Peijun Hou, Yanli Wang, Ting Leung Sham

Mechanical Properties and Mechanics

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

1 Scopus citations

Abstract

High-temperature reactor structural components are often under the complex multiaxial creep-fatigue (CF) loading conditions throughout the lifetime because of geometric and/or metallurgical discontinuities and complex loading paths. To assess the multiaxial CF deformation behavior and to evaluate the CF design rules in the ASME BPVC Section III, Division 5, Subsection HB, Subpart B, experimental and numerical studies are performed on Alloy 617 at 950°C using notch specimen geometries under CF loading in this study. Two types of notch specimen geometries, shallow-notch and sharp V-notch were designed for Alloy 617 per ASTM Standard E292-09. Experimental procedures were developed, and tests at 950°C were performed under CF loading with tension hold time using the two notch specimen geometries. The information collected from the experiments included the average axial stress relaxation histories, the changes in the relaxation behavior as a function of applied cycles, and failure information. Additionally, an inelastic constitutive model of Alloy 617 was used in the finite element analyses of the notch specimens to determine the stress triaxiality distributions, local and average stress relaxation behavior, and local elastic follow-up. The results from the experimental and numerical studies on the CF of notch specimens are compared with those on standard uniaxial smooth bar specimens. The notch effect on the CF deformation and failure of Alloy 617 is summarized and the assessment of the design rules regarding the treatment of multiaxial stress relaxation is discussed.

Original language	English
Title of host publication	Codes and Standards
Publisher	American Society of Mechanical Engineers (ASME)
ISBN (Electronic)	9780791887448
DOIs	https://doi.org/10.1115/PVP2023-106503
State	Published - 2023
Event	ASME 2023 Pressure Vessels and Piping Conference, PVP 2023 - Atlanta, United States Duration: Jul 16 2023 → Jul 21 2023

Publication series

Name	American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Volume	1
ISSN (Print)	0277-027X

Conference

Conference	ASME 2023 Pressure Vessels and Piping Conference, PVP 2023
Country/Territory	United States
City	Atlanta
Period	07/16/23 → 07/21/23

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 Charles S. Hawkins and Brad Hall of ORNL in running the experiments is greatly appreciated. The research was sponsored by the U.S. Department of Energy, Office of Nuclear Energy, under contract No. DE-AC05-00OR22725 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 Charles S. Hawkins and Brad Hall of ORNL in running the experiments is greatly appreciated. This manuscript has been co-authored by Battelle Energy Alliance, LLC, under Contract No. DE-AC07-05ID14517 and by UT-Battelle LLC, under Contract No. DE-AC0500OR22725, with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes.

Keywords

Alloy 617
Elastic follow-up
High temperature
Multiaxial Creep-fatigue
Notch
Stress triaxiality

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10.1115/PVP2023-106503

Cite this

@inproceedings{80422ffa65834063ac485f7bab1e0b90,

title = "NOTCH EFFECT ON CREEP-FATIGUE BEHAVIOR OF ALLOY 617 AT ELEVATED TEMPERATURE",

abstract = "High-temperature reactor structural components are often under the complex multiaxial creep-fatigue (CF) loading conditions throughout the lifetime because of geometric and/or metallurgical discontinuities and complex loading paths. To assess the multiaxial CF deformation behavior and to evaluate the CF design rules in the ASME BPVC Section III, Division 5, Subsection HB, Subpart B, experimental and numerical studies are performed on Alloy 617 at 950°C using notch specimen geometries under CF loading in this study. Two types of notch specimen geometries, shallow-notch and sharp V-notch were designed for Alloy 617 per ASTM Standard E292-09. Experimental procedures were developed, and tests at 950°C were performed under CF loading with tension hold time using the two notch specimen geometries. The information collected from the experiments included the average axial stress relaxation histories, the changes in the relaxation behavior as a function of applied cycles, and failure information. Additionally, an inelastic constitutive model of Alloy 617 was used in the finite element analyses of the notch specimens to determine the stress triaxiality distributions, local and average stress relaxation behavior, and local elastic follow-up. The results from the experimental and numerical studies on the CF of notch specimens are compared with those on standard uniaxial smooth bar specimens. The notch effect on the CF deformation and failure of Alloy 617 is summarized and the assessment of the design rules regarding the treatment of multiaxial stress relaxation is discussed.",

keywords = "Alloy 617, Elastic follow-up, High temperature, Multiaxial Creep-fatigue, Notch, Stress triaxiality",

author = "Peijun Hou and Yanli Wang and Sham, {Ting Leung}",

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year = "2023",

doi = "10.1115/PVP2023-106503",

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Hou, P, Wang, Y & Sham, TL 2023, NOTCH EFFECT ON CREEP-FATIGUE BEHAVIOR OF ALLOY 617 AT ELEVATED TEMPERATURE. in Codes and Standards., v001t01a057, American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP, vol. 1, American Society of Mechanical Engineers (ASME), ASME 2023 Pressure Vessels and Piping Conference, PVP 2023, Atlanta, United States, 07/16/23. https://doi.org/10.1115/PVP2023-106503

NOTCH EFFECT ON CREEP-FATIGUE BEHAVIOR OF ALLOY 617 AT ELEVATED TEMPERATURE. / Hou, Peijun; Wang, Yanli; Sham, Ting Leung.
Codes and Standards. American Society of Mechanical Engineers (ASME), 2023. v001t01a057 (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP; Vol. 1).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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AU - Wang, Yanli

AU - Sham, Ting Leung

PY - 2023

Y1 - 2023

N2 - High-temperature reactor structural components are often under the complex multiaxial creep-fatigue (CF) loading conditions throughout the lifetime because of geometric and/or metallurgical discontinuities and complex loading paths. To assess the multiaxial CF deformation behavior and to evaluate the CF design rules in the ASME BPVC Section III, Division 5, Subsection HB, Subpart B, experimental and numerical studies are performed on Alloy 617 at 950°C using notch specimen geometries under CF loading in this study. Two types of notch specimen geometries, shallow-notch and sharp V-notch were designed for Alloy 617 per ASTM Standard E292-09. Experimental procedures were developed, and tests at 950°C were performed under CF loading with tension hold time using the two notch specimen geometries. The information collected from the experiments included the average axial stress relaxation histories, the changes in the relaxation behavior as a function of applied cycles, and failure information. Additionally, an inelastic constitutive model of Alloy 617 was used in the finite element analyses of the notch specimens to determine the stress triaxiality distributions, local and average stress relaxation behavior, and local elastic follow-up. The results from the experimental and numerical studies on the CF of notch specimens are compared with those on standard uniaxial smooth bar specimens. The notch effect on the CF deformation and failure of Alloy 617 is summarized and the assessment of the design rules regarding the treatment of multiaxial stress relaxation is discussed.

AB - High-temperature reactor structural components are often under the complex multiaxial creep-fatigue (CF) loading conditions throughout the lifetime because of geometric and/or metallurgical discontinuities and complex loading paths. To assess the multiaxial CF deformation behavior and to evaluate the CF design rules in the ASME BPVC Section III, Division 5, Subsection HB, Subpart B, experimental and numerical studies are performed on Alloy 617 at 950°C using notch specimen geometries under CF loading in this study. Two types of notch specimen geometries, shallow-notch and sharp V-notch were designed for Alloy 617 per ASTM Standard E292-09. Experimental procedures were developed, and tests at 950°C were performed under CF loading with tension hold time using the two notch specimen geometries. The information collected from the experiments included the average axial stress relaxation histories, the changes in the relaxation behavior as a function of applied cycles, and failure information. Additionally, an inelastic constitutive model of Alloy 617 was used in the finite element analyses of the notch specimens to determine the stress triaxiality distributions, local and average stress relaxation behavior, and local elastic follow-up. The results from the experimental and numerical studies on the CF of notch specimens are compared with those on standard uniaxial smooth bar specimens. The notch effect on the CF deformation and failure of Alloy 617 is summarized and the assessment of the design rules regarding the treatment of multiaxial stress relaxation is discussed.

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NOTCH EFFECT ON CREEP-FATIGUE BEHAVIOR OF ALLOY 617 AT ELEVATED TEMPERATURE

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