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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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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惰性基质燃料MgONd2(Zr1-xCex)2O7复合陶瓷的Kr10+辐照稳定性和应变积累

本文对惰性基质燃料的潜在基体MgONd2(Zr1-xCex)2O7 （M-NZCx）复合陶瓷进行了3.5 MeV Kr10+辐照，辐照量为1 × 1014-5 × 1015离子/cm2。系统地研究了辐照后M-NZCx复合陶瓷中由焦绿石(P)向缺陷萤石(F)结构的相变（P-F转变），以及MgO和焦绿石相的晶格膨胀、非晶化和应变积累。具体来说，在相同的Kr10+浓度照射下，M-NZCx样品中不同相的晶格膨胀比（Rs）为：RsM <；负责& lt;无国界记者。对典型M-NZC0.3样品中不同相辐照响应的进一步研究表明，MgO对焦绿盐相具有优越的辐照稳定性。Kr10+轰击引起的应变积累在MgO和NZC0.3焦绿石相中普遍存在，且MgO晶中缺陷诱导的应变比NZC0.3焦绿石相更为明显。有趣的是，Kr10+辐照引起的应变积累倾向于沿低原子密度方向取向。本研究为了解MgONd2Zr2O7基复合陶瓷在氪离子弹性碰撞级联中的辐照稳定性提供了新的视角。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.