Hydrogen redistribution in non-irradiated and irradiated duplex zirconium claddings by high-resolution neutron imaging

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

Journal of Nuclear Materials Pub Date : 2025-03-25 DOI:10.1016/j.jnucmat.2025.155780

Okan Yetik , Pavel Trtik , Robert Zubler , Robin Manuel Grabherr , Johannes Bertsch , Liliana I. Duarte

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Abstract

Duplex claddings, a concept with an outer layer on Zircaloy-4 substrate, have been employed in Swiss pressurized water reactors for decades. A significant amount of spent fuel encapsulated within this cladding type is currently stored in interim dry storage facilities before relocation to deep geological repositories. Duplex claddings exhibit different hydrogen distribution behaviour compared to single material claddings. This behaviour has been previously observed in non-irradiated duplex claddings. In this study, we extended the investigation to reactor-irradiated duplex cladding with an average burnup of 71.6 MWd/kg (HM). The results show that chemical potential and terminal solid solubility influence hydrogen distribution in both non-irradiated and reactor-irradiated cladding. However, the initial distribution of hydrogen plays a significant role in its subsequent redistribution. The formation of a dense hydride accumulation zone in the liner (DHAZ_liner) is evident and arises from differences in hydrogen solubility between the liner and substrate. Irradiated claddings demonstrate higher hydrogen mobility within the cladding, making them more responsive to external stresses in comparison to non-irradiated claddings.

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用高分辨率中子成像研究未辐照和辐照双锆包层中氢的再分布

双层包层是一种外层是锆合金-4衬底的概念，已经在瑞士的压水堆中应用了几十年。在转移到深层地质储存库之前，在这种包壳类型中封装的大量乏燃料目前储存在临时干储存设施中。双包层表现出与单包层不同的氢分布行为。这种行为以前已经在未辐照的双层包层中观察到。在这项研究中，我们将研究扩展到平均燃耗为71.6 MWd/kg （HM）的反应堆辐照双层包层。结果表明，化学势和末端固溶度对未辐照和反应堆辐照包层中氢的分布都有影响。然而，氢的初始分布在随后的再分布中起着重要的作用。在衬里（DHAZliner）中形成致密的氢化物积聚带是明显的，这是由于衬里和底物之间氢溶解度的差异造成的。经过辐照的包层在包层内表现出更高的氢迁移率，与未辐照的包层相比，使它们对外部应力的响应更灵敏。

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.