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.
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。