通过弱监督学习实现核燃料芯块表面裂纹检测方法

IF 1.5 4区工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Journal of Nuclear Science and Technology Pub Date : 2024-07-07 DOI:10.1080/00223131.2024.2371961

Fengyu Li, Bin Zhang, Bin Zhang, Fanghui Zhang, Qingtao Zhao, Shiyang Lou, Zhiyong Wang, Kaixin Huang

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引用次数: 0

摘要

表面裂纹是核燃料芯块的主要缺陷之一，对核安全生产构成重大危害。最近开发的基于深度学习的裂纹检测和分析方法可用于核燃料芯块的表面裂纹检测。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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Implementation of surface crack detection method for nuclear fuel pellets by weakly supervised learning

Surface cracks are one of the primary defects in nuclear fuel pellets, posing a significant hazard to nuclear safety production. Deep learning-based methods recently developed for crack detection a...

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来源期刊

Journal of Nuclear Science and Technology 工程技术-核科学技术

CiteScore

2.40

自引率

16.70%

发文量

116

审稿时长

2.3 months

期刊介绍： The Journal of Nuclear Science and Technology (JNST) publishes internationally peer-reviewed papers that contribute to the exchange of research, ideas and developments in the field of nuclear science and technology, to contribute peaceful and sustainable development of the World. JNST ’s broad scope covers a wide range of topics within its subject category, including but are not limited to: General Issues related to Nuclear Power Utilization: Philosophy and Ethics, Justice and Policy, International Relation, Economical and Sociological Aspects, Environmental Aspects, Education, Documentation and Database, Nuclear Non-Proliferation, Safeguard Radiation, Accelerator and Beam Technologies: Nuclear Physics, Nuclear Reaction for Engineering, Nuclear Data Measurement and Evaluation, Integral Verification/Validation and Benchmark on Nuclear Data, Radiation Behaviors and Shielding, Radiation Physics, Radiation Detection and Measurement, Accelerator and Beam Technology, Synchrotron Radiation, Medical Reactor and Accelerator, Neutron Source, Neutron Technology Nuclear Reactor Physics: Reactor Physics Experiments, Reactor Neutronics Design and Evaluation, Reactor Analysis, Neutron Transport Calculation, Reactor Dynamics Experiment, Nuclear Criticality Safety, Fuel Burnup and Nuclear Transmutation, Reactor Instrumentation and Control, Human-Machine System: Reactor Instrumentation and Control System, Human Factor, Control Room and Operator Interface Design, Remote Control, Robotics, Image Processing Thermal Hydraulics: Thermal Hydraulic Experiment and Analysis, Thermal Hydraulic Design, Thermal Hydraulics of Single/Two/Multi Phase Flow, Interactive Phenomena with Fluid, Measurement Technology...etc.