首页> 外文会议>International conference on environmental degradation of materials in nuclear power systems-water reactors >THE EFFECTS OF METALLURGICAL FACTORS ON STRESS CORROSION CRACK GROWTH RATE IN SIMULATED PWR PRIMARY WATER FOR COLD WORKED TT ALLOY 690
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THE EFFECTS OF METALLURGICAL FACTORS ON STRESS CORROSION CRACK GROWTH RATE IN SIMULATED PWR PRIMARY WATER FOR COLD WORKED TT ALLOY 690

机译:冶金因素对冷轧TT合金690模拟压水堆原水中应力腐蚀裂纹扩展速率的影响

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It is well known that the stress corrosion crack growth rate (SCCGR) in simulated PWR primary water for cold worked TT Alloy 690 shows significant scatter from heat-to-heat. Authors have pointed out that the metallurgical factors due to the fabrication process are very important for understanding the heat-to-heat SCCGR differences in simulated PWR primary water. In this paper, the SCCGRs were measured for various laboratory heats and commercial heats for control rod drive mechanism (CRDM) tube materials. The cracks and voids at grain boundary carbides were carefully observed by scanning electron microscopy (SEM) and transmission electron microscopy (TEM), to estimate the SCCGR of various hot finished thermally treated (TT) Alloy 690 materials that were subsequently cold rolled based on their metallurgical characteristics. Furthermore, the behavior of primary M_(23)C_6 carbides in simulated PWR primary water was studied to clarify the mechanism of PWSCC for hot finished and highly cold worked TT Alloy 690. From this study, it became clear that the PWSCCGR depends not only on cold work and grain size but also on the number of micro cracks and voids in or near primary carbides, etc. In addition, the cracked large primary M_(23)C_6 carbides should be dissolved by simulated PWR primary water, and M_(23)C_6 might be changed to oxides such as (Cr, Ni)Fe_2O_4. The SCCGR for highly cold worked after hot worked TT Alloy 690 including primary carbides may be affected by this dissolving and changing process.
机译:众所周知,冷加工的TT合金690在模拟的PWR初级水中的应力腐蚀裂纹扩展速率(SCCGR)显示出从热到热的显着散布。作者指出,由于制造工艺而产生的冶金因素对于理解模拟压水堆原水的热-热SCCGR差异非常重要。在本文中,对SCCGR进行了各种实验室加热和控制棒驱动机构(CRDM)管材料的商业加热的测量。通过扫描电子显微镜(SEM)和透射电子显微镜(TEM)仔细观察了晶界碳化物的裂纹和空隙,以评估各种热精加工热处理(TT)合金690材料的SCCGR,然后根据其材料对其进行冷轧冶金特性。此外,研究了在模拟的PWR初级水中初级M_(23)C_6碳化物的行为,以阐明热加工和高冷加工TT合金690的PWSCC机理。从这项研究中,很明显,PWSCCGR不仅取决于冷加工和晶粒尺寸,还涉及初级碳化物内或附近的微裂纹和空隙的数量等。此外,应通过模拟的PWR初级水和M_(23)溶解开裂的大型M_(23)C_6初级碳化物。 C_6可能会更改为氧化物,例如(Cr,Ni)Fe_2O_4。在热加工的TT合金690(包括原始碳化物)之后的高度冷加工的SCCGR可能会受到该溶解和变化过程的影响。

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