Continuum Damage Mechanics Modeling of High-Temperature Flaw Propagation: Application to Creep Crack Growth In 316H Standardized Specimens and Nuclear Reactor Components

Recuero, Antonio; Petkov, Markian; Spencer, Benjamin W.; Juan, Pierre-Alexandre

doi:10.1115/1.4062953

Continuum Damage Mechanics Modeling of High-Temperature Flaw Propagation: Application to Creep Crack Growth In 316H Standardized Specimens and Nuclear Reactor Components

Journal Article · Tue Jul 11 00:00:00 EDT 2023 · Journal of Pressure Vessel Technology

DOI:https://doi.org/10.1115/1.4062953· OSTI ID:1992084

Recuero, Antonio ^[1]; Petkov, Markian ^[2]; Spencer, Benjamin W. ^[1]; Juan, Pierre-Alexandre ^[2]

Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Kairos Power LLC, Alameda, CA (United States)

Predicting creep crack growth (CCG) of flaws found during operation in high-temperature alloy components is essential for assessing the remaining lifetime of those components. While defect assessment procedures are available for this purpose in design codes, these are limited in their range of applicability. This study assesses the application of a local damage-based finite-element methodology as a more general technique for the prediction of CCG at high temperatures on a variety of structural configurations. Numerical results for stainless steel 316H, which are validated against experimental data, show the promise of this approach. This integration of continuum damage mechanics (CDM) based methodologies, together with adequate inelastic models, into assessment procedures can therefore inform the characterization of CCG under complex operating conditions, while avoiding excessive conservatism. This article shows that such modeling frameworks can be calibrated to experimental data and used to demonstrate that the degree of tri-axiality ahead of a growing creep crack affects its rate of growth. The framework is also successfully employed in characterizing CCG in a realistic reactor pressure vessel geometry under an arbitrary loading condition. These results are particularly relevant to the nuclear power industry for defect assessment and inspections as part of codified practices of structural components with flaws in high-temperature reactors.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: U.S. Industry Opportunities for Advanced Nuclear Technology Development; USDOE Office of Nuclear Energy (NE), Nuclear Science User Facilities (NSUF)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1992084

Report Number(s):: INL/JOU-23-71598-Rev000

Journal Information:: Journal of Pressure Vessel Technology, Journal Name: Journal of Pressure Vessel Technology Journal Issue: 5 Vol. 145; ISSN 0094-9930

Publisher:: ASMECopyright Statement

Country of Publication:: United States

Language:: English

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Continuum Damage Mechanics Modeling of High-Temperature Flaw Propagation: Application to Creep Crack Growth In 316H Standardized Specimens and Nuclear Reactor Components

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