Hydrogen charging effects on the oxidation of Alloy 690 with different cold rolling degrees in high temperature water environment

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

Journal of Nuclear Materials Pub Date : 2025-04-08 DOI:10.1016/j.jnucmat.2025.155812

ShiChen Wei , Xu Wang , Xiangguo Li , Haijing Sun , Jian Xu , Testuo Shoji

引用次数: 0

Abstract

The effects of H charging on Alloy 690 were investigated under different cold rolling degrees in high-temperature water. The study examined changes in the thickness of the inner oxide layer under different cold rolling degrees. During the cold rolling process, Cr diffusivity demonstrated minimal variation as a result of the competing effects between increased dislocation density and the transition from high-angle grain boundaries (HAGBs) to low angle grain boundaries (LAGBs). The interaction between H and the microstructure during the cold rolling process influences the oxidation of Alloy 690. The presence of interstitial H atoms in dislocations and grain boundaries inhibits the outward diffusion of Cr³⁺ while simultaneously promoting oxidation. However, with increased cold rolling and microband formation, many dislocations are generated, offering new paths for Cr element diffusion to the surface.

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加氢对690合金不同冷轧度在高温水环境下氧化的影响

研究了高温水中不同冷轧程度下充氢对690合金的影响。研究了不同冷轧程度下内氧化层厚度的变化。在冷轧过程中，由于位错密度增加和高角晶界向低角晶界转变的相互作用，Cr的扩散系数变化很小。冷轧过程中H与组织的相互作用影响690合金的氧化。位错和晶界中间隙H原子的存在抑制了Cr³⁺的向外扩散，同时促进了氧化。然而，随着冷轧和微带形成的增加，产生了许多位错，为Cr元素向表面扩散提供了新的途径。

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.