Reliability assessment of nuclear reactor heat transfer tubes under stress corrosion degradation and shocks based on the Markov renewal process

The reliability of nuclear reactor steam generator heat transfer tubes subjected to stress corrosion and shock damage has emerged as a critical area of focus in reactor structural safety research. This study develops a reliability analysis model that incorporates the bidirectional interaction mechanism between degradation and shock damage, formulated within the framework of the Markov renewal process. State-dependent equivalent stress level parameters are introduced to quantify this interaction mechanism. For the cumulative shock failure mode, a numerical analysis method based on the Laplace transform is proposed, with its accuracy validated through Monte Carlo simulation. Case study findings demonstrate that incorporating the damage interaction mechanism yields a more conservative reliability assessment of heat transfer tubes compared to assessments that omit this mechanism. The outcomes of this research provide theoretical guidance for the integrity evaluation of critical nuclear reactor structures, prediction of remaining service life, and formulation of operation and maintenance strategies.

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Publication Details

Journal
IET conference proceedings.
Published
2025-12-01
DOI
https://doi.org/10.1049/icp.2025.3591
Primary Topic
Nuclear Engineering Thermal-Hydraulics
Type
article
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article

Reliability assessment of nuclear reactor heat transfer tubes under stress corrosion degradation and shocks based on the Markov renewal process

Xiaofan Sun, Yu Jie, Daochuan Ge, Shaoxuan Wang et al.
IET conference proceedings.
Nuclear Engineering Thermal-Hydraulics
article

Reliability assessment of nuclear reactor heat transfer tubes under stress corrosion degradation and shocks based on the Markov renewal process

Xiaofan Sun, Yu Jie, Daochuan Ge, Shaoxuan Wang, Zhixin Xu, Jinkai Wang
article en

Abstract

The reliability of nuclear reactor steam generator heat transfer tubes subjected to stress corrosion and shock damage has emerged as a critical area of focus in reactor structural safety research. This study develops a reliability analysis model that incorporates the bidirectional interaction mechanism between degradation and shock damage, formulated within the framework of the Markov renewal process. State-dependent equivalent stress level parameters are introduced to quantify this interaction mechanism. For the cumulative shock failure mode, a numerical analysis method based on the Laplace transform is proposed, with its accuracy validated through Monte Carlo simulation. Case study findings demonstrate that incorporating the damage interaction mechanism yields a more conservative reliability assessment of heat transfer tubes compared to assessments that omit this mechanism. The outcomes of this research provide theoretical guidance for the integrity evaluation of critical nuclear reactor structures, prediction of remaining service life, and formulation of operation and maintenance strategies.

IET conference proceedings.Vol. 2025(35)
University of Science and Technology of China (CN), Hefei Institutes of Physical Science (CN), China General Nuclear Power Corporation (China) (CN), Key Laboratory of Nuclear Radiation and Nuclear Energy Technology (CN), State Nuclear Power Technology Company (China) (CN)
Openalex Percentile: Top 48%
Nuclear Engineering Thermal-Hydraulics
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