预测铀化合物热导率的多类分类模型

IF 1.5 4区 工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Science and Technology Pub Date : 2023-10-20 DOI:10.1080/00223131.2023.2269974
Y. Sun, M. Kumagai, M. Jin, E. Sato, M. Aoki, Y. Ohishi, K. Kurosaki
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引用次数: 0

摘要

摘要先进核燃料旨在提供更好的性能和事故容忍度,重点是实现更高的导热性。虽然像氮化铀、碳化物和硅化铀等有前途的候选燃料已被广泛研究,但大多数铀化合物仍未被开发。为了在这些未开发的铀化合物中寻找潜在的候选物质,我们结合了机器学习来加速材料发现过程。在这项研究中,我们训练了一个多类别分类模型,基于133个来自元素性质和温度的输入特征来预测化合物的导热系数。最初的训练数据由来自Starrydata2数据库的超过16万条经过处理的导热性记录组成,但是数据类分布的倾斜导致训练模型低估了化合物的导热性。因此,我们通过应用合成少数过采样技术和随机欠采样来解决类别不平衡问题,将导热系数高于15 W/mK的材料的召回率从0.64提高到0.71。最后,利用我们的最佳模型在774种稳定的铀化合物中识别出119种具有高导热性的潜在先进候选燃料。我们的结果强调了机器学习在核科学领域的潜力,加速了先进核材料的发现。关键词:先进核燃料机器学习导热性免责声明作为对作者和研究人员的服务,我们提供此版本的已接受手稿(AM)。在最终出版版本记录(VoR)之前,将对该手稿进行编辑、排版和审查。在制作和印前,可能会发现可能影响内容的错误,所有适用于期刊的法律免责声明也与这些版本有关。披露声明作者未报告潜在的利益冲突。数据可用性声明支持本研究结果的数据可在https://github.com/AzarashiYifan/classification-uranium-thermal-conductivity.Additional information上公开获取。资助本工作由MEXT创新核研究与发展计划资助号JPMXD0220354330和JPMXD0222682541支持。
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A multiclass classification model for predicting the thermal conductivity of uranium compounds
ABSTRACTAdvanced nuclear fuels are designed to offer improved performance and accident tol- erance, with an emphasis on achieving higher thermal conductivity. While promising fuel candidates like uranium nitrides, carbides, and silicides have been widely stud- ied, the majority of uranium compounds remain unexplored. To search for potential candidates among these unexplored uranium compounds, we incorporated machine learning to accelerate the material discovery process. In this study, we trained a multiclass classification model to predict a compound’s thermal conductivity based on 133 input features derived from element properties and temperature. The initial training data consists of over 160,000 processed thermal conductivity records from the Starrydata2 database, but a skewed data class distribution led the trained model to underestimate compound’s thermal conductivity. Consequently, we addressed the issue of class imbalance by applying Synthetic Minority Oversampling TEchnique and Random UnderSampling, improving the recall for materials with thermal con- ductivity higher than 15 W/mK from 0.64 to 0.71. Finally, our best model is used to identify 119 potential advanced fuel candidates with high thermal conductivity among 774 stable uranium compounds. Our results underscore the potential of ma- chine learning in the field of nuclear science, accelerating the discovery of advanced nuclear materials.KEYWORDS: Advanced nuclear fuelsMachine learningthermal conductivityDisclaimerAs a service to authors and researchers we are providing this version of an accepted manuscript (AM). Copyediting, typesetting, and review of the resulting proofs will be undertaken on this manuscript before final publication of the Version of Record (VoR). During production and pre-press, errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal relate to these versions also. Disclosure statementNo potential conflict of interest was reported by the author(s).Data availability statementThe data that support the findings of this study are openly available at https://github.com/AzarashiYifan/classification-uranium-thermal-conductivity.Additional informationFundingThis work was supported by MEXT Innovative Nuclear Research and Development Program Grant Number JPMXD0220354330 and JPMXD0222682541.
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来源期刊
Journal of Nuclear Science and Technology
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.
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