The role of material modeling on strain range estimation for elevated temperature cyclic life evaluation

M. C. Messner; R. I. Jetter; T. L. Sham; Yanli Wang

doi:10.1115/PVP201884100

The role of material modeling on strain range estimation for elevated temperature cyclic life evaluation

M. C. Messner, R. I. Jetter, T. L. Sham, Yanli Wang

Mechanical Properties and Mechanics

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

Abstract

High temperature nuclear reactors operating in the creep regime are designed to withstand numerous cyclic events. Current ASME code rules provide two basic paths for evaluating creep fatigue and ratcheting under these conditions; one based on full inelastic analysis intended to provide a representative stress and strain history and the other based on elastic material models with adjustments of varying complexity to account for inelastic stress and strain redistribution. More recent developments have used elastic-perfectly plastic analysis to bound the effects of cyclic service. However, these methods still rely on the separate evaluation of fatigue and creep damage utilizing a damage interaction diagram. There is a procedure under current development that uses creep-fatigue data from key feature test articles directly without the use of the damage interaction diagram. However, it requires a reasonable representation of the strain range in a structure as an input. This work develops a simplified procedure based on elastic perfectly-plasticity analysis that can be used to represent the strain range in a structure in the steady state under cyclic loading conditions.

Original language	English
Title of host publication	Codes and Standards
Publisher	American Society of Mechanical Engineers (ASME)
ISBN (Electronic)	9780791851593
DOIs	https://doi.org/10.1115/PVP201884100
State	Published - 2018
Event	ASME 2018 Pressure Vessels and Piping Conference, PVP 2018 - Prague, Czech Republic Duration: Jul 15 2018 → Jul 20 2018

Publication series

Name	American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Volume	1B-2018
ISSN (Print)	0277-027X

Conference

Conference	ASME 2018 Pressure Vessels and Piping Conference, PVP 2018
Country/Territory	Czech Republic
City	Prague
Period	07/15/18 → 07/20/18

Funding

This manuscript has been co-authored by UChicago Argonne LLC under Contract No. DE-AC02-06CH11357, and by UT-Battelle LLC, under Contract No. DE-AC05-00OR22725, 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. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan: (http://energy.gov/downloads/doe-public-access-plan). The research was sponsored by the U.S. Department of Energy, under Contract No. DE-AC02-06CH11357 with Argonne National Laboratory, managed and operated by UChicago Argonne LLC, and under contract DE-AC05-00OR22725 with Oak Ridge National Laboratory, managed and operated by UT-Battelle LLC. Programmatic direction was provided by the Office of Nuclear Energy.

Funders	Funder number
UChicago Argonne LLC
UT-Battelle LLC
U.S. Department of Energy	DE-AC02-06CH11357
Argonne National Laboratory	DE-AC05-00OR22725
Oak Ridge National Laboratory

Access to Document

10.1115/PVP201884100

Cite this

Messner, M. C., Jetter, R. I., Sham, T. L., & Wang, Y. (2018). The role of material modeling on strain range estimation for elevated temperature cyclic life evaluation. In Codes and Standards (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP; Vol. 1B-2018). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/PVP201884100

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title = "The role of material modeling on strain range estimation for elevated temperature cyclic life evaluation",

abstract = "High temperature nuclear reactors operating in the creep regime are designed to withstand numerous cyclic events. Current ASME code rules provide two basic paths for evaluating creep fatigue and ratcheting under these conditions; one based on full inelastic analysis intended to provide a representative stress and strain history and the other based on elastic material models with adjustments of varying complexity to account for inelastic stress and strain redistribution. More recent developments have used elastic-perfectly plastic analysis to bound the effects of cyclic service. However, these methods still rely on the separate evaluation of fatigue and creep damage utilizing a damage interaction diagram. There is a procedure under current development that uses creep-fatigue data from key feature test articles directly without the use of the damage interaction diagram. However, it requires a reasonable representation of the strain range in a structure as an input. This work develops a simplified procedure based on elastic perfectly-plasticity analysis that can be used to represent the strain range in a structure in the steady state under cyclic loading conditions.",

author = "Messner, {M. C.} and Jetter, {R. I.} and Sham, {T. L.} and Yanli Wang",

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year = "2018",

doi = "10.1115/PVP201884100",

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Messner, MC, Jetter, RI, Sham, TL & Wang, Y 2018, The role of material modeling on strain range estimation for elevated temperature cyclic life evaluation. in Codes and Standards. American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP, vol. 1B-2018, American Society of Mechanical Engineers (ASME), ASME 2018 Pressure Vessels and Piping Conference, PVP 2018, Prague, Czech Republic, 07/15/18. https://doi.org/10.1115/PVP201884100

The role of material modeling on strain range estimation for elevated temperature cyclic life evaluation. / Messner, M. C.; Jetter, R. I.; Sham, T. L. et al.
Codes and Standards. American Society of Mechanical Engineers (ASME), 2018. (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP; Vol. 1B-2018).

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

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N2 - High temperature nuclear reactors operating in the creep regime are designed to withstand numerous cyclic events. Current ASME code rules provide two basic paths for evaluating creep fatigue and ratcheting under these conditions; one based on full inelastic analysis intended to provide a representative stress and strain history and the other based on elastic material models with adjustments of varying complexity to account for inelastic stress and strain redistribution. More recent developments have used elastic-perfectly plastic analysis to bound the effects of cyclic service. However, these methods still rely on the separate evaluation of fatigue and creep damage utilizing a damage interaction diagram. There is a procedure under current development that uses creep-fatigue data from key feature test articles directly without the use of the damage interaction diagram. However, it requires a reasonable representation of the strain range in a structure as an input. This work develops a simplified procedure based on elastic perfectly-plasticity analysis that can be used to represent the strain range in a structure in the steady state under cyclic loading conditions.

AB - High temperature nuclear reactors operating in the creep regime are designed to withstand numerous cyclic events. Current ASME code rules provide two basic paths for evaluating creep fatigue and ratcheting under these conditions; one based on full inelastic analysis intended to provide a representative stress and strain history and the other based on elastic material models with adjustments of varying complexity to account for inelastic stress and strain redistribution. More recent developments have used elastic-perfectly plastic analysis to bound the effects of cyclic service. However, these methods still rely on the separate evaluation of fatigue and creep damage utilizing a damage interaction diagram. There is a procedure under current development that uses creep-fatigue data from key feature test articles directly without the use of the damage interaction diagram. However, it requires a reasonable representation of the strain range in a structure as an input. This work develops a simplified procedure based on elastic perfectly-plasticity analysis that can be used to represent the strain range in a structure in the steady state under cyclic loading conditions.

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The role of material modeling on strain range estimation for elevated temperature cyclic life evaluation

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