Kr10+ irradiation stability and strain accumulation of MgONd2(Zr1-xCex)2O7 composite ceramics for inert matrix fuel

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

Journal of Nuclear Materials Pub Date : 2025-03-01 DOI:10.1016/j.jnucmat.2025.155722

Yijie Tang , Jin Wang , Junxia Wang , Long Kang , Tongming Zhang , Jun Li , Yan Wang , Xusheng Li , Yanping Yang

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引用次数: 0

Abstract

In this work, MgONd₂(Zr_1-_xCe_x)₂O₇ (M-NZC_x) composite ceramics, a potential matrix, used for inert matrix fuel were subjected to 3.5 MeV Kr¹⁰⁺ irradiation with fluences of 1 × 10¹⁴–5 × 10¹⁵ ions/cm². The phase transition from pyrochlore (P) to defect fluorite (F) structures (P-F transition) in NZC_x phase, as well as the lattice expansion, amorphization and strain accumulation in both MgO and pyrochlore phases in post-irradiated M-NZC_x composite ceramics were systematically investigated. Specifically, the lattice expansion ratios (Rs) of different phases in M-NZC_x samples irradiated with the same fluence of Kr¹⁰⁺ ions were ranged as follows, Rs_M < Rs_P < Rs_F. The further research on irradiation response of different phases in typical M-NZC_0.3 sample indicated that MgO exhibited superior irradiation stability to pyrochlore phase. Additionally, the strain accumulation induced by Kr¹⁰⁺ bombardment was observed generally in both MgO and NZC_0.3 pyrochlore phases, and the defect-induced strain in MgO crystalline was more pronounced than NZC_0.3 pyrochlore phase. Interestingly, the strain accumulation resulting from Kr¹⁰⁺ irradiation was observed to be preferentially oriented along directions with lower atomic density. This study might provide a new perspective for understanding the irradiation stability of MgONd₂Zr₂O₇ based composite ceramics in elastic collision cascade by krypton ions.

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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.