首页> 外文会议>International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors >A Mechanistic Study of Stress Corrosion Crack Propagation in Heavily Cold Worked TT Alloy 690 Exposed to Simulated PWR Primary Water
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A Mechanistic Study of Stress Corrosion Crack Propagation in Heavily Cold Worked TT Alloy 690 Exposed to Simulated PWR Primary Water

机译:沉重的冷加工TT合金690中应力腐蚀裂纹传播的机械研究,暴露于模拟PWWR初级水

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The Stress Corrosion Crack Growth Rate (SCCGR) in heavily cold rolled Thermally Treated (TT) Alloy 690 exposed to simulated PWR primary water at 360 °C increases with increasing cold rolling ratio, but the SCCGR in cold rolled Mill Annealed (MA) Alloy 690 remains very low, regardless of cold rolling ratio. Cavities were detected near GB carbides in heavily cold rolled TT Alloy 690 before the SCC tests. There is a good correlation between the existence of cavities near GB carbides and high SCCGRs in heavily cold rolled TT Alloy 690. The number of cavities increases with increasing cold rolling ratio and is affected by heating in air at 400 or 475 °C for ~2000 h and by exposure in simulated PWR primary water at 360 °C. However, the cavities were detected not only in the stressed area but also in the stress-free area of the SCC test specimens of heavily cold rolled TT Alloy 690. By contrast, the effect of Ni content on SCCGRs in Ni base (25-30%)-Cr-Fe alloys is not significant for similar amounts of GB carbide precipitation. The high SCCGRs in heavily cold rolled TT Alloy 690 may be caused by a high density of lattice defects, cavities near GB carbides, cracking of M_(23)C_6 primary GB carbides, and hydrogen absorption, but there is no possibility of creep damage at the test temperature of 360 °C. More detailed tests will be needed to confirm this hypothesis.
机译:耐应力腐蚀裂纹扩展速率(SCCGR)在重冷轧热处理(TT)690合金暴露于模拟的PWR主水在360℃随着冷轧比C的增加,但在寒冷的SCCGR轧制轧制退火(MA)690合金仍然很低,无论冷轧率。在SCC测试之前,在重冷轧TT合金690附近GB碳化物检测腔。有在重冷邻近GB碳化物腔和高SCCGRs的存在之间的良好相关性冷轧TT合金690的随冷轧率增加空腔的数目并通过在400或475℃,〜2000在空气中加热的影响小时,通过在360℃下暴露于模拟的PWR主水。然而,检测腔不仅强调面积,而且在受到大量冷食的SCC试样的无应力区域推出TT合金690与此相反,在镍基SCCGRs Ni含量的影响(25-30 %) - 铬 - 铁合金不是相似量GB碳化物析出的显著。在重冷高SCCGRs轧制TT合金690可以由晶格缺陷,邻近GB碳化物空腔,M_开裂的高密度引起的(23)C_6初级GB碳化物和氢的吸收,但没有在蠕变损伤的可能性试验温度为360℃。更详细的测试将需要确认这种假设。

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