摘要
针对超低碳奥低体不锈钢堆焊材料,采用带极电渣堆焊工艺,应用600 MW核容器标准热处理规范——615℃×29h深入研究了堆焊层晶间相析出的机理研究结果表明经615℃×29h热处理后,堆焊层晶间析出了少量的M_(23)C_6碳化物和Y′相未发现σ相、相和X相等金属间脆性化合物.少量M_(23)C_6碳化物的析出,不致于严重影响堆焊层的性能.
For the ultra - low - carbon austenitic stainless steel, using the process of strip electrode electroslag surfacing and the standardized heat treatment process of 600 MW nuclear vessels (615℃×29 h) , the mechanism of grain boundary phase eduction in weld metal is analysed deeply. The research results indicate that there is a little M23 C6 carbonide does not seriously influence the properties of weld metal.
出处
《焊接》
1999年第12期18-21,共4页
Welding & Joining
关键词
带极电渣堆焊
铁索体
碳化物
Σ相
不锈钢
堆焊
strip electrode electroslag surfacing, ferrite, carbonide, a phase
