首页> 外文会议>European Corrosion Congress >Stress Corrosion Cracking Growth Rate of Cold Rolled Thermally Treated Alloy 690 and Solution Annealed Alloy 690 and their Mechanisms in Simulated PWR Primary Water
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Stress Corrosion Cracking Growth Rate of Cold Rolled Thermally Treated Alloy 690 and Solution Annealed Alloy 690 and their Mechanisms in Simulated PWR Primary Water

机译:冷轧热处理合金690和溶液退火合金690的应力腐蚀裂解速率及其在模拟PWW初级水中的机制

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The Stress Corrosion Cracking Growth Rate (SCCGR) measurement tests and high-resolutional scanning electron microscopy, etc., were conducted on the many level of cold rolled (CR) Thermally Treated (TT) or solution annealed (SA) Alloy 690 and mill annealed (MA) Alloy 600 using commercial heats and laboratory heats, to clarify the mechanism on the large SCCGR for heavily CR TT Alloy 690. The number of micro-cavities near grain boundary (GB) carbides is strongly affected by the CR ratio. They are not detected in ≤ 10% CR commercial TT Alloy 690, in CR SA Alloy 690 and in ≤ 20% CR MA Alloy 600 (no or small number of GB carbides). No stress dependency for their formation was observed. The formation of micro-cavities in CR TT Alloy 690 is unrelated to creep damage. However, the number of micro-cavities near GB carbides in heavily CR TT Alloy 690 increased with increasing of time or temperature heated in air or exposure at 360°C in simulated PWR primary water and with increasing of Hydrogen concentration in simulated PWR primary water. The SCCGRs of CR TT Alloy 690 at 360°C in simulated PWR primary water show the good correlation with the number of micro-cavities near GB carbides in CR TT Alloy 690. Micro-cavities ner GB carbides in the TT Alloy 690 are deduced to be generated by shear strain due to CR. A high density of lattice defects is observed near GB carbides after CR and they agglomerate near GB carbides during heating at temperatures where lattice defects are sufficiently mobile. New micro-cavities or coarse cavities can be generated by heating and stabilized by Hydrogen absorbed from simulated PWR primary water. Nevertheless, in case of ≤ 10% CR (the likely upper limit of effective CR in practical components), the generation of micro-cavities near GBs is negligible.
机译:在诸多水平的冷轧(CR)热处理(TT)或溶液退火(SA)合金690和磨机上进行应力腐蚀裂解速率(SCCRG)测量试验和高分辨率扫描电子显微镜等。 (MA)合金600使用商业热量和实验室热量,阐明大型CR TT合金690的大型SCCGR的机制。晶界附近的微空腔数(GB)碳化物受Cr比的强烈影响。它们在≤10%CR商业TT合金690中未检测到CR SA合金690和≤20%CR MA合金600(NO或少量GB碳化物)中。没有观察到它们的形成没有压力依赖性。 CR TT合金690中微腔的形成与蠕变损坏无关。然而,在Simulated PR初级水中在空气或在360℃下在空气或暴露中加热的时间或温度的时间或温度的增加以及模拟PWR初级水中的氢浓度的增加,增加了GB碳化物的微空腔的数量增加。在模拟PWR初级水中360℃的Cr TT合金690的SCCRS显示出与CR TT合金690中的GB碳化物附近的微空腔数量的良好相关性。TT合金690中的微空腔Ner GB碳化物被推导出来由Cr引起的剪切菌株产生。在CR之后在GB碳化物附近观察到高密度的晶格缺陷,并且在晶格缺陷足够移动的温度下加热期间,它们在加热期间附近GB碳化物附近。通过从模拟PWR初级水吸收的氢气加热和稳定,可以产生新的微腔或粗糙腔。然而,在≤10%Cr(在实际组件中有效CR的可能上限)的情况下,在GB附近的微腔的产生可忽略不计。

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