Micromechanical response of SiC-OPyC layers in TRISO fuel particles

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-01 Epub Date: 2025-01-23 DOI:10.1016/j.jnucmat.2025.155654
Katherine I. Montoya, Erik G. Herbert, Danny P. Schappel, Christian M. Petrie, Andrew T. Nelson, Tyler J. Gerczak
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Abstract

Tristructural isotropic (TRISO)–coated particle fuel is a proposed fuel for multiple advanced reactor concepts. The performance of the particle depends on whether the silicon carbide (SiC) layer remains intact to prevent the release of metallic and gaseous fission products. Mechanical fracture of the SiC layer is a potential failure mode under various fuel configurations and operating environments, including the potential transmission of matrix-originating cracks through TRISO particles. This study uses instrumented indentation techniques on cross-sectioned surrogate particles to examine the mechanical stability of the critical interface between SiC and the outer pyrolytic carbon (OPyC) layer. The observed behavior at the interface is rationalized by examining the radially dependent fracture behavior of the SiC layer and performing a numerical analysis to quantify the residual stresses that develop during the processing and cross-sectioning of the as-fabricated particle. Characterizing the SiC-OPyC interface of surrogate TRISO particles using nanoindentation provides unique insight into the interface's room-temperature residual stress and mechanical stability. The modeling efforts were used to investigate the experimental procedure further, and the results are presented herein to validate this fuel form's potential mechanical failure modes.
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SiC-OPyC层在TRISO燃料颗粒中的微观力学响应
三结构各向同性(TRISO)包覆颗粒燃料是一种用于多种先进反应堆概念的燃料。颗粒的性能取决于碳化硅(SiC)层是否保持完整,以防止金属和气体裂变产物的释放。SiC层的机械断裂是在各种燃料配置和操作环境下的一种潜在失效模式,包括基体源裂纹通过TRISO颗粒的潜在传递。本研究使用仪器压痕技术在横截面替代颗粒上检测SiC和外层热解碳(OPyC)层之间关键界面的机械稳定性。通过检查SiC层的径向相关断裂行为,并进行数值分析来量化在加工和制造颗粒的横截面过程中产生的残余应力,从而使观察到的界面行为合理化。利用纳米压痕表征替代TRISO颗粒的SiC-OPyC界面,为界面的室温残余应力和机械稳定性提供了独特的见解。在此基础上,对实验过程进行了进一步的研究,并给出了验证该燃料形态潜在机械失效模式的结果。
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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