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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2013.1
- 수록면
- 67 - 72 (6page)
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Stress corrosion cracking (SCC) behaviors of Alloy 690 were studied in lead-containing aqueous alkaline solutions using the slow strain rate tension (SSRT) tests in 0.1M and 2.5M NaOH with and without PbO at 315oC. The side and fracture surfaces of the alloy were then examined using scanning electron microscopy after the SSRT test. Microstructure and composition of the surface oxide layer were analyzed by using a field emission transmission electron microscopy, equipped with an energy dispersive X-ray spectroscopy. Even though Alloy 690 was almost immune to SCC in 0.1M NaOH solution,irrespective of PbO addition, the SCC resistance of Alloy 690 decreased in a 2.5M NaOH solution and further decreased by the addition of PbO. Based on thermodynamic stability and solubility of oxide, high Cr of 30wt% in the Alloy 690 is favorable to SCC in mild alkaline and acidic solutions whereas the SCC resistance of high Cr Alloy 690 is weakened drastically in the strong alkaline solution where the oxide is not stable any longer and solubility is too high to form a passive oxide locally.
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참고문헌 (16)
참고문헌 신청
/ / HSC Chemistry Database, 6.0
/ 2003 / NUREG report
A. Baum / 2005 / / Proc. of 12th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems- Water Reactors : 1155 ~ 1162
D.-J. Kim / 2010 / / J. Nanoscience and Nanotechnology 10 : 85 ~ 91
D.-J. Kim / 2011 / / Corrosion Science 53 : 1247 ~ 1253
/ 2003 / NUREG report
A. Baum / 2005 / / Proc. of 12th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems- Water Reactors : 1155 ~ 1162
D.-J. Kim / 2010 / / J. Nanoscience and Nanotechnology 10 : 85 ~ 91
D.-J. Kim / 2011 / / Corrosion Science 53 : 1247 ~ 1253
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