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成分和热处理对核级不锈钢堆焊材料氧化行为的影响

Influence of composition and heat treatment on oxidation behavior of nuclear grade stainless steel cladding materials

  • 摘要: 利用SEM,XRD和XPS等手段研究了二种核级不锈钢堆焊材料在350 ℃/22 MPa高温高压水中的氧化行为. 结果表明,随着腐蚀周期的增加,不锈钢堆焊材料表面氧化物颗粒数量逐渐增多,氧化物颗粒尺寸逐渐增大,氧化膜厚度逐渐增加;不锈钢堆焊材料表面氧化膜为外层富铁内层富铬的双层结构,氧化膜组成成分主要为Fe-Cr氧化物;Cr元素含量的增加会降低材料表面氧化物颗粒的数量和氧化膜厚度, 而焊后热处理(PWHT)增加了材料表面氧化物颗粒的数量和氧化膜厚度.

     

    Abstract: The oxidation behavior on two kinds of nuclear grade stainless claddings in 350 ℃/22 MPa high temperature and high pressure water were carried out by SEM, XRD and XPS. The results show that, with increase of oxidation duration, the number and the size of oxide particles as well as the thickness of the oxide film increase slowly. The oxide film formed on the surface of the stainless steel cladding materials exhibits bi-layer structure with Fe-rich outer layer and Cr-rich inner layer, and contains Fe-Cr oxides mainly. The number of the oxide particles and the thickness of the oxide film decrease with increase of Cr content, while post-weld heat treatment (PWHT) contributes to the increase of the number of the oxide particles and the thickness of the oxide film.

     

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