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对核电用304L奥氏体不锈钢进行450℃×6 h等离子体源渗氮处理,对比研究了渗氮前后改性层的组织与性能。结果表明:304L奥氏体不锈钢渗氮后,表面获得了厚度约为15μm,峰值氮浓度可达25at%的单一面心结构的γ_Ν相改性层,其最大显微硬度高达1320 HV0.025,干摩擦条件下,γ_Ν相改性层的磨损体积由原始不锈钢的0.102 mm~3降低至9.26×10~(-3)mm~3,磨损机制由黏着磨损转变为氧化磨损,耐磨性能显著提高。在3.5%Na Cl溶液和p H=8.4硼酸溶液中,γ_Ν相改性层的自腐蚀电位比原始不锈钢分别提高了323 m V和75 m V,耐蚀性能明显改善。
The nitriding of 304L austenitic stainless steel for nuclear power at 450 ℃ for 6 h was studied. The microstructure and properties of the modified layer before and after nitriding were compared. The results show that after the nitriding of 304L austenitic stainless steel, the γ_N phase modified layer with a single facet structure with a thickness of about 15μm and a peak nitrogen concentration of up to 25at% can be obtained. The maximum microhardness is up to 1320 HV 0.025, Under the condition of dry friction, the wear volume of γ_N phase modified layer decreased from 0.102 mm ~ 3 to 9.26 × 10 ~ (-3) mm ~ 3, the wear mechanism changed from adhesive wear to oxidative wear, and the wear resistance was significantly increased . In 3.5% NaCl solution and p H = 8.4 boric acid solution, the corrosion potential of the γ_N modified layer was improved by 323 mV and 75 mV respectively compared with the original stainless steel.