Thermo-mechanical evaluation of UO2-SiC fuel rod in hypothetical accidents using COMSOL multiphysics

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-11-18 DOI:10.1016/j.nucengdes.2024.113717

M. Sharifi, M. Aghaie

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Abstract

In this research, the COMSOL is used as a multi-physics software to simulate the thermo-mechanical performance of a UO₂-SiC fuel rod in hypothetical accidents of WWERs. First, by using the thermal and mechanical analysis, the temperature, strain and stress in different parts of the UO₂-SiC fuel rod in normal operation are calculated. Next the performance of fuel rod in hypothetical reactivity insertions and hypothetical semi loss of coolant is evaluated. The results of the thermal and mechanical analysis of UO₂-SiC fuel with different percentages of SiC and the substitution of Si instead of zirconium clad are also analyzed. Coupling point kinetic equations with COMSOL events related to the increase in reactor power, such as the reactivity insertion accident (RIA), are simulated. For more detail study, hydrogen diffusion in the clad, oxygen diffusion in the fuel and non-stoichiometric fuels are considered. Finally, a sensitivity analysis is carried out to see how the effective quantities affect the mechanical and thermal evaluations and COMSOL is introduced as a multi physics software could present accident evaluations.

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利用 COMSOL 多物理场对假设事故中的 UO2-SiC 燃料棒进行热机械评估

本研究使用 COMSOL 作为多物理场软件，模拟二氧化铀-碳化硅燃料棒在 WWER 假设事故中的热机械性能。首先，通过热分析和力学分析，计算出正常运行时二氧化硅-碳化硅燃料棒不同部位的温度、应变和应力。然后评估了燃料棒在假设的反应性插入和假设的冷却剂半损失情况下的性能。此外，还分析了不同碳化硅比例的二氧化铀-碳化硅燃料的热分析和机械分析结果，以及用硅代替锆包层的结果。模拟了与反应堆功率增加有关的耦合点动力学方程和 COMSOL 事件，如反应性插入事故（RIA）。为了进行更详细的研究，还考虑了堆芯中的氢扩散、燃料中的氧扩散以及非化学计量燃料。最后，还进行了敏感性分析，以了解有效量对机械和热评估的影响，并介绍了 COMSOL 作为一种可进行事故评估的多物理软件。

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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来源期刊

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.