辐照碳化硅热导率和体积膨胀的计算框架

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Daxi Guo, Hengfeng Gong, Mingzhou Chen, Yinghong Chen, Shihuai Wang, Jianhan Zhai, Xiansheng Zhang, Yan Yan, Zhiwei Lu, Jiwei Wang, Jiaxiang Xue, Yehong Liao, Guoliang Zhang
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引用次数: 0

摘要

采用分子动力学(MD)模拟方法研究了SiC中缺陷的产生和积累过程,建立了473 ~ 1073 K温度下SiC中缺陷演化的动力学模型。模拟结果表明,辐照温度的升高降低了SiC的缺陷产生效率,抑制了缺陷的积累。模型计算的热导率和膨胀率与等温辐照实验结果吻合较好。热导率和膨胀在温度变化下的演化表明,当前模型克服了等温模型在短瞬态时间内随温度非物理同步演化的缺点。对典型轻水堆加载条件下SiC熔覆层的热力学分析表明,本文提出的模型与现有模型预测的稳态功率下的应力分布和演化相似,而以往的等温模型低估了反应堆关闭/功率下降期间的应力,高估了功率上升期间的应力。结果表明,该模型可用于燃料性能分析,尤其适用于反应堆停堆和功率斜坡等温度突变情况。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Computational framework for thermal conductivity and volumetric swelling of irradiated silicon carbide
Defect production and accumulation in SiC has been studied by molecular dynamics (MD) simulations, and a kinetic model has been developed for defect evolution in SiC in the temperature regime of 473 K to 1073 K. Simulations show that the increase in irradiation temperature diminishes the defect production efficiency of SiC and suppresses the defect accumulation. Thermal conductivity and swelling calculated by the model show good agreement with isothermal irradiation experiments. Evolution of thermal conductivity and swelling under varying temperature shows that the current model can overcome the drawback of isothermal models in terms of unphysical concurrent evolution with temperature during short transient. Thermo-mechanical analysis of SiC cladding under typical LWR loading conditions reveals that the proposed model and the existing models predict similar stress distribution and evolution under steady power, while the stress is underestimated during reactor shutdown/power ramp-down and overestimated during power ramp-up by the previous isothermal model. The results indicate that the proposed model can be applied to the fuel performance analysis especially for cases with abrupt temperature changes such as reactor shutdown and power ramp.
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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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