Fuel performance simulations of TRISO particle geometries derived from XCT

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
M. Poschmann, A. Prudil, R. Osmond
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引用次数: 0

Abstract

The current AGR TRISO fuel specification effectively assumes that the layer thickness variations within a particle do not significantly affect particle performance. However, the limits of this assumption and their relevance for commercial TRISO production have not been established. In this work, a method was developed to generate 3D geometries of TRISO particles, including the spatial variation in layer thickness, from X-ray computed tomography for use in fuel performance modelling. Simulated irradiation of a demonstration particle found SiC hoop stress values peaking at 315 MPa in tension, significantly in excess of those from previous modelling studies with similar particle aspect ratios. Simulations with representative 2D axisymmetric geometries based on the demonstration particle predicted significantly lower stresses for the same simulated irradiation. 2D radial segments extracted with an arbitrarily oriented polar axis under-predicted the maximum SiC hoop stress by 315-400 MPa, while those extracted with the polar axis passing through the point of maximum SiC hoop stress in the 3D model under-predicted the maximum SiC hoop stress by 165-275 MPa. The 2D model produced using existing methods for generating a 2D flat-spot particle under-predicted the maximum SiC hoop stress by 215 MPa. These findings suggest that existing models may underestimate the stress caused by the asphericity of certain TRISO particle morphologies, and that the current AGR specification may not capture all of the geometric factors that contribute to particle failure probability.
从 XCT 得出的 TRISO 粒子几何形状的燃料性能模拟
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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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