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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2019.1
- 수록면
- 228 - 237 (10page)
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초록· 키워드
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The crack growth responses of as-received and as-welded Alloy 600/182 and Alloy 690/152 welds toconstant loading were measured by a direct current potential drop method using compact tensionspecimens in primary water at 325 C simulating the normal operating conditions of a nuclear powerplant. The as-received Alloy 600 showed crack growth rates (CGRs) between 9.6 10 9 mm/s and3.8 10 8 mm/s, and the as-welded Alloy 182 had CGRs between 7.9 10 8 mm/s and 7.5 10 7 mm/swithin the range of the applied loadings. These results indicate that Alloys 600 and 182 are susceptible tocracking. The average CGR of the as-welded Alloy 152 was found to be 2.8 10 9 mm/s. Therefore, Alloy152 was proven to be highly resistant to cracking. The as-received Alloy 690 showed no crack growtheven with an inhomogeneous banded microstructure. The cracking mode of Alloys 600 and 182 was anintergranular cracking; however, Alloy 152 was revealed to have a mixed (intergranular þ transgranular)cracking mode. It appears that the Cr concentration and the microstructural features significantly affectthe cracking resistance and the cracking behavior of Ni-base alloys in PWR primary water
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참고문헌 (26)
참고문헌 신청
W. Bamford / 2003 / A review of Alloy 600 cracking in operating nuclear plants:historical experience and future trends / Proc. of the 11th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-water Reactor :1071~1079
W. Bamford / 2005 / Cracking of Alloy 600 nozzles and welds in PWRs: review of cracking events and repair service experience / Proc. of the 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-water Reactor :959~965
Y. S. Lim / 2013 / Microstructural characterization of intergranular stress corrosion cracking of Alloy 600 in PWR primary water environment / J. Nucl. Mater 440:46~54
V. Y. Gertsman / 2001 / Study on grain boundary character along intergranular stress corrosion crack paths in austenitic alloys / Acta Mater 49:1589~1598
L.E. Thomas / 2009 / Microstructural characterization of primary water stress-corrosion cracks in Alloy 182 welds from PWR components and laboratory tests / Proceedings of the 14th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-water Reactor :409~421
W. Bamford / 2005 / Cracking of Alloy 600 nozzles and welds in PWRs: review of cracking events and repair service experience / Proc. of the 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-water Reactor :959~965
Y. S. Lim / 2013 / Microstructural characterization of intergranular stress corrosion cracking of Alloy 600 in PWR primary water environment / J. Nucl. Mater 440:46~54
V. Y. Gertsman / 2001 / Study on grain boundary character along intergranular stress corrosion crack paths in austenitic alloys / Acta Mater 49:1589~1598
L.E. Thomas / 2009 / Microstructural characterization of primary water stress-corrosion cracks in Alloy 182 welds from PWR components and laboratory tests / Proceedings of the 14th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-water Reactor :409~421
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