采用电化学动电位再活化(EPR)法以及ASTM GZ8一A失重法研究了形变量及热处理工艺对核电厂蒸汽发生器传热管用国产镍基690合金晶间腐蚀性能影响.试样经过3%～10%的形变后,在1080℃、1100℃、1120℃温度加热10 min和15 min固溶处理,最后经715℃,10 h时效热处理.不同条件处理的试样室温下在0.5 mol/LH2SO4+0.01 mol/L KSCN溶液中进行了EPR扫描;经2%溴+98%甲醇溶液浸蚀后对690合金进行晶界形貌观察.结果表明,时效处理能显著改变晶间碳化物形态,改善690合金耐腐蚀性能;形变3%、1120℃保持10 min固溶处理的试样,形变5%、1100℃保持10 min固溶处理的试样以及形变5%、1120℃保持15 min固溶处理的试样在所测试的条件下再活化率和腐蚀速率较低.
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