首页> 外文会议>International Conference on Environmental degradation of Materials in Nuclear Power Systems-Water Reactors >ONE DIMENSIONAL COLD ROLLING EFFECTS ON STRESS CORROSION CRACK GROWTH IN ALLOY 690 TUBING AND PLATE MATERIALS
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ONE DIMENSIONAL COLD ROLLING EFFECTS ON STRESS CORROSION CRACK GROWTH IN ALLOY 690 TUBING AND PLATE MATERIALS

机译:一维冷轧效果对合金690管和板材的应力腐蚀裂纹增长

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Stress corrosion crack-growth experiments have been performed on cold-rolled alloy 690 materials in simulated PWR primary water at 360°C. Extruded alloy 690 CRDM tubing in two conditions, thermally treated (TT) and solution annealed (SA), was cold rolled (CR) in one direction to several reductions reaching a maximum of 31% and tested in the S-L orientation. High stress corrosion cracking (SCC) propagation rates (~8x 10~(-8) mm/s) were observed for the 31%CR alloy 690TT material, while the 31%CR alloy 690SA exhibited 10X lower rates. The difference in intergranular SCC susceptibility appears to be related to grain boundary carbide distribution before cold rolling. SCC growth rates were found to depend on test temperature and hydrogen concentration. Tests were also performed on two alloy 690 plate heats, one CR to a reduction of 26% and the other to 20%. SCC growth rates at 360°C were similar to that measured for the 31%CR alloy 690TT CRDM tubing. Comparisons will be made to other results on CR alloy 690 materials.
机译:在360℃下,在模拟PWR初级水中对冷轧合金690材料进行了应力腐蚀裂纹 - 生长实验。挤出合金690 CRDM管在两个条件下,热处理(TT)和溶液退火(SA),在一个方向上冷轧(CR),以达到最多31%并在S-L方向上测试。对于31%Cr合金690TT材料,观察到高应力腐蚀裂解(SCC)传播速率(〜8×10〜(-8)mm / s),而31%Cr合金690SA率显示出10倍。晶间SCC易感性的差异似乎与冷轧前的晶界碳化物分布有关。发现SCC生长速率取决于测试温度和氢浓度。还对两种合金690板热量进行了试验,一个CR降低26%,另外为20%。 360℃的SCC生长速率类似于31%Cr合金690TT CRDM管测量的速率。将对Cr合金690材料的其他结果进行比较。

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