Insights into 1200 °C steam oxidation behavior of Cr coatings with different microstructure on Zircaloy-4 alloys for enhanced accident tolerant fuel cladding

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2024-08-27 DOI:10.1016/j.anucene.2024.110885

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Abstract

In order to improve the 1200°C steam oxidation properties of Cr-coated zirconium alloy accident tolerant fuel cladding tubes, chromium coatings with various micro-structures were fabricated by bipolar high-power impulse magnetron sputtering technology. The microstructures of chromium coatings transforms from unconsolidated column structure to dense & column-oblate structure with the bias voltage increase. Hardness and elastic modulus values of optimal chromium coatings are approximately 19.1 GPa and 374.8 GPa, respectively, which are 2.09 and 1.60 times higher than those of chromium coatings with unconsolidated column structures. Optimal chromium coatings with dense & column-oblate structures display preferable 1200°C steam oxidation resistance because of possession lower weight gain value and thicker Cr₂O₃ oxide layer after 2 h exposure periods. The fabrication strategy of chromium coatings with dense & column-oblate structure is expected to pave the way for enhancing 1200 °C steam oxidation resistance for Cr-coated zirconium alloys.

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对 Zircaloy-4 合金上不同微观结构铬涂层 1200 °C 蒸汽氧化行为的深入研究，以提高燃料包壳的事故耐受性

为了改善铬涂层锆合金事故耐受燃料包壳管的 1200°C 蒸汽氧化性能，采用双极高功率脉冲磁控溅射技术制备了具有各种微结构的铬涂层。随着偏置电压的增加，铬镀层的微观结构由未固结的柱状结构转变为致密的&柱状-oblate结构。最佳铬镀层的硬度值和弹性模量值分别约为 19.1 GPa 和 374.8 GPa，分别是未固结柱状结构铬镀层的 2.09 倍和 1.60 倍。具有致密&；柱状-卵圆形结构的最佳铬涂层具有更佳的 1200°C 蒸汽抗氧化性，因为其在 2 小时暴露期后具有更低的增重值和更厚的 Cr2O3 氧化层。具有致密和柱状扁平结构的铬涂层的制造策略有望为提高铬涂层锆合金的 1200°C 蒸汽抗氧化性铺平道路。

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

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.