Study of pellet-clad bonding using heat treatment of axially cut slices of PWR fuel rod

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-02-01 DOI:10.1016/j.jnucmat.2024.155540

L. Desgranges, J. Sercombe, Y. Pontillon

引用次数: 0

Abstract

Slices of high burn-up nuclear fuel rod were prepared with or without an axial slit in the cladding or a central hole in the fuel. After identical heat treatment at 1200 °C, slices with cut cladding exhibited a wide opening of the slit while the uncut slices showed no major change of their cladding. Post-test examination evidenced that a layer made of High Burn-up Structure remained adherent to the cladding. Mechanical simulations indicated that this bonded HBS layer could be the reason for the cladding opening. These results confirmed that the HBS can be very tightly adherent to the cladding, as postulated in previous literature.

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来源期刊

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.