Crack path analysis of spent nuclear fuel cladding using the strain energy-based Dijkstra algorithm

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-12-01 Epub Date: 2024-10-30 DOI:10.1016/j.nucengdes.2024.113661
Jee A Baik, Jung Jin Kim
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Abstract

The integrity of spent fuel cladding is crucial for preventing the release of radioactive materials, which pose significant risks to public safety and the environment. However, accurately predicting cracks in cladding tubes remains a challenge. This study proposes a novel method for predicting crack paths in spent nuclear fuel cladding tubes using the Dijkstra algorithm, based on strain energy. In this method, cladding images are segmented into cladding and hydride pixels, followed by a finite element analysis to calculate the strain energy. The Dijkstra algorithm utilizes this strain energy data from hydrides to predict crack paths in areas with low resistance to loading. The predicted path exhibited an accuracy of 92.78 % with respect to the initiation point of the actual crack path and was located within 200 μm of the actual crack path. The proposed method demonstrates a higher similarity to the actual crack path than conventional image-based methods. These results suggest that the safety assessment of spent nuclear fuel can be enhanced, enabling the development of effective management strategies for spent nuclear fuel.

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利用基于应变能的 Dijkstra 算法分析乏核燃料包壳的裂纹路径
乏燃料包壳的完整性对于防止放射性物质泄漏至关重要,而放射性物质泄漏会给公共安全和环境带来重大风险。然而,准确预测包壳管中的裂纹仍然是一项挑战。本研究提出了一种基于应变能、使用 Dijkstra 算法预测乏核燃料包壳管裂纹路径的新方法。在这种方法中,包壳图像被分割为包壳和氢化物像素,然后进行有限元分析以计算应变能。Dijkstra 算法利用来自氢化物的应变能数据来预测负载阻力较低区域的裂纹路径。与实际裂纹路径的起始点相比,预测路径的准确率为 92.78%,并且位于实际裂纹路径的 200 μm 范围内。与传统的基于图像的方法相比,所提出的方法与实际裂纹路径的相似度更高。这些结果表明,可以加强乏核燃料的安全评估,从而制定有效的乏核燃料管理策略。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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