A cumulative damage model for tubes in nuclear power plants subject to continuous degradation and multi-effect shocks under dynamic environments

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-08-13 DOI:10.1016/j.anucene.2024.110839
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Abstract

Continuous degradation and shocks are two vital damage mechanisms for tubes under dynamic environments in nuclear power plants (NPPs). In this work, we presented a cumulative damage model to evaluate the reliability of tubes in NPPs, which accounts for continuous degradation and random shocks. The dynamic environments were assumed to obey a homogenous Markov process. Continuous degradation was described as a general stochastic process with independent increments. A multinomial distribution was used to depict the multiple effects of Poisson-distributed shocks on tubes. The influence of dynamic environments on the cumulative damage process of tubes was also explicitly modeled. Closed-form reliability measures were derived, such as reliability functions and mean time to failure (MTTF) of tubes. Drawing upon a case study from the existing literature, the analytical solution was validated through a comparative analysis with the outcomes of Monte Carlo simulation (MCS) and other methodologies referenced in the literature. As a practical engineering application, the reliability of steam generator tubes made of Alloy 690 within pressurized water reactors (PWRs), which are susceptible to primary side stress corrosion cracking (PWSCC) and the effects of water hammer, was calculated. The findings indicate that the probabilities of steam generator tube rupture (SGTR) as estimated by the model and those inferred from operational experience have the same order of magnitude.

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动态环境下受持续退化和多效应冲击影响的核电站管道累积损伤模型
在核电站(NPPs)的动态环境下,连续降解和冲击是管道的两种重要损坏机制。在这项工作中,我们提出了一个累积损伤模型,用于评估核电站管道的可靠性,该模型考虑了连续退化和随机冲击。假设动态环境服从同质马尔可夫过程。连续退化被描述为具有独立增量的一般随机过程。多项式分布用于描述泊松分布冲击对管道的多重影响。此外,还明确模拟了动态环境对钢管累积损坏过程的影响。得出了闭式可靠性度量,如可靠性函数和钢管平均失效时间(MTTF)。利用现有文献中的一个案例研究,通过与蒙特卡罗模拟(MCS)结果和文献中提到的其他方法进行比较分析,验证了分析解决方案。在实际工程应用中,计算了压水反应堆(PWRs)中由合金 690 制成的蒸汽发生器管子的可靠性,这些管子容易受到一次侧应力腐蚀开裂(PWSCC)和水锤的影响。结果表明,模型估算的蒸汽发生器管破裂 (SGTR) 的概率与根据运行经验推断的概率具有相同的数量级。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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