AGR-5/6/7辐照实验胶囊1 Compact中脱固结TRISO粒子的x射线计算机断层扫描

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-03-01 Epub Date: 2025-02-19 DOI:10.1016/j.jnucmat.2025.155704
Rahul Reddy Kancharla , William C. Chuirazzi , Joshua J. Kane , John D. Stempien , Cameron Howard , Swapnil Morankar , Miles T. Cook , Quintin D. Harris
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引用次数: 0

摘要

对AGR-5/6/7辐照实验1号胶囊的燃料Compact 1-7-9中的三iso颗粒进行了x射线计算机断层扫描(XCT)。紧凑型1-7-9位于过热的热电偶附近,热电偶释放过渡金属,并在胶囊1的区域内造成TRISO颗粒的严重损坏和失效。四个粒子,粒子A-D,在三维(3D)上进行无损检测。粒子B被发现含有降解的碳化硅(SiC)和大量的Ni、锕系元素以及导致这种降解的裂变产物。镍(Ni)从碳化硅层的外表面渗透到粒子B中。对颗粒A、C和D的核进行了尺寸、形状和孔隙度分析。在核中观察到密度梯度,这可能是在较高辐照温度的燃料中观察到的初生核迁移。除了核外,颗粒A、C和D还具有大量密集的物质团簇,这些物质团簇主要集中在颗粒的一侧,位于缓冲/内热解碳界面。通过扫描电镜(SEM)和电子色散x射线能谱(EDS)证实,这些团簇是由于镍迁移到颗粒内部造成的。
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X-ray computed tomography of deconsolidated TRISO Particles from the AGR-5/6/7 irradiation experiment capsule 1 Compact
X-ray Computed Tomography (XCT) was performed on TRISO particles from fuel Compact 1-7-9 from Capsule 1 of the AGR-5/6/7 irradiation experiment. Compact 1–7–9 was in the vicinity of overheated thermocouples that released transition metals and caused significant damage and failure of TRISO particles within regions of Capsule 1. Four particles, Particles A–D, were non-destructively examined in three-dimensions (3D). Particle B was found to have degraded silicon carbide (SiC) and significant amounts of Ni, actinides, and fission products that contributed to this degradation. The nickel (Ni) showed some evidence of penetration into Particle B from the exterior surface of the silicon carbide layer. The kernels of Particles A, C, and D were analyzed for their size, shape, and observed porosity. A density gradient was observed in the kernels, which may be nascent kernel migration observed in fuel with higher irradiation temperatures. In addition to the kernels, Particles A, C, and D possessed large clusters of dense material that were grouped primarily to one side of the particle located at the buffer/inner pyrolytic carbon interface. These clusters were attributed to nickel migration into the particle interiors, which was confirmed with scanning electron microscopy (SEM) and electron dispersive X-ray spectroscopy (EDS).
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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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