Machine learning - assisted prediction of yield strength in irradiated type 316 stainless steels

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-10-19 DOI:10.1016/j.fusengdes.2024.114691
Ziqiang Wang , Chen Yang , Ning Gao , Xuebang Wu , Zhongwen Yao
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Abstract

The investigation into irradiation hardening and embrittlement is of critical importance in nuclear material subject. This work explores the applications of machine learning (ML) to predict the yield strength of irradiated type 316 stainless steels. A dataset comprising 354 samples is compiled through an extensive review of prior experimental studies. Each sample has 23 potentially influential features. Five distinct machine learning models are trained and evaluated. Among these models, the Gradient Boosting (GB) model demonstrates superior prediction performance and robust stability. The prominent factors identified by the GB model are in reasonable agreement with established knowledge regarding the determinants of yield strength in irradiated type 316 stainless steels. These findings provide critical insights into the mechanical properties of irradiated type 316 stainless steels.
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机器学习--辅助预测辐照型 316 不锈钢的屈服强度
研究辐照硬化和脆化对核材料课题至关重要。这项研究探索了机器学习(ML)在预测辐照 316 型不锈钢屈服强度方面的应用。通过对先前实验研究的广泛回顾,编制了由 354 个样本组成的数据集。每个样本都有 23 个潜在的影响特征。对五个不同的机器学习模型进行了训练和评估。在这些模型中,梯度提升(GB)模型表现出卓越的预测性能和强大的稳定性。GB 模型确定的突出因素与有关辐照 316 型不锈钢屈服强度决定因素的已有知识相当吻合。这些发现为了解辐照 316 型不锈钢的机械性能提供了重要依据。
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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