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锻造态316LN不锈钢在模拟压水堆一回路水中的初期氧化行为 被引量:1

Initial Oxidation Behavior of Forged 316LN Stainless Steel in Simulated PWR Primary Water
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摘要 利用扫描电镜(SEM)、X射线光电子谱技术(XPS)、和X射线衍射(XRD)技术,分析了国产锻造态316LNSS在加氢高温高压水中浸泡480 h后表面氧化膜的形貌和化学成分。结果表明,氧化膜最外层主要分布两种不同尺寸的氧化物颗粒,大尺寸氧化物(~1 mm)分布较为稀疏,而小尺寸氧化物(200~300 nm)分布非常紧密;锻造态316LNSS表面形成外层富Fe、内层富Cr的双层结构氧化膜,外层氧化膜主要由Fe3O4和少量氢氧化物(Ni(OH)2和CrOOH等)组成,内层氧化膜主要由富Cr尖晶石结构氧化物组成。同时讨论了316LNSS在模拟压水堆一回路水中的氧化机制。 Forged 316 LNSS has been selected as the main pipe line material used in the third generation nuclear power plants. The oxide scale formed on the forged 316 LNSS after immersion in high temperature pressurized water with 2.3 mg/L of dissolved hydrogen(DH) was studied using scanning electron microscopy(SEM), X-ray diffraction(XRD) and X-ray photoelectron spectroscopy(XPS). Results showed that a double-layer oxide scale was grown on 316 LNSS. The outer Ferich layer was composed of Fe3O4 and hydroxides(mainly Ni(OH)2and CrOOH) and the inner layer was composed of Cr-enriched spinel oxides. The mechanism of oxide scale formation was also discussed.
出处 《腐蚀科学与防护技术》 CAS CSCD 北大核心 2015年第4期313-320,共8页 Corrosion Science and Protection Technology
基金 国家科技重大专项课题项目(2011ZX06004-009)资助
关键词 核电材料 不锈钢 锻造 氧化膜 腐蚀 高温高压水 nuclear material stainless steel forging oxide film corrosion high temperature pressurized water
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