SCC analysis of Alloy 600 tubes from a retired steam generator
Source abstract
Abstract
Abstract Steam generators (SG) equipped with Alloy 600 tubes of a Korean nuclear power plants were replaced with a new one having Alloy 690 tubes in 1998 after 20 years of operation. To set up a guide line for an examination of the other SG tubes, a metallographic examination of the defected tubes was carried out. A destructive analysis on 71 tubes was addressed, and a relation among the stress corrosion crack (SCC) defect location, defect depth, and location of the sludge pile was obtained. Tubes extracted from the retired SG were transferred to a hot laboratory. Detailed nondestructive analysis examinations were taken again at the laboratory, and the tubes were then destructively examined. The types and sizes of the cracks were characterized. The location and depth of the SCC were evaluated in terms of the location and height of the sludge. Most axial cracks were in the sludge pile, whereas the circumferential ones were around the top of the tube sheet (TTS) or below the TTS. Average defect depth of the axial cracks was deeper than that of the circumferential ones. Axial cracks at tube support plate (TSP) seem to be related with corrosion/sludge in crevice like at the TTS region. Circumferential cracks at TSP seem to be caused by tube denting at the upper part of the TSP.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Fatigue and fracture mechanics · Non-Destructive Testing Techniques
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (17)
Show source-provided references
1. Chae · Korea Atomic Energy Research Institute · 1989
2. EPRI · 1997
3. Hunt · 1994
4. Grimmel · 2005
5. Shah · Nuclear Engineering and Design · 1992 · 134 · 19210.1016/0029-5493(92)90139-M ↗
6. IAEA · 2011
7. Hwang · Corrosion · 2003 · 59 · 82110.5006/1.3277611 ↗
8. J.P.N. Paine, U.E. Gustafsson, Steam Generator Reference Book, rev. 1, vol. 1, EPRI TR-103824s-V1R1, Electric Power Research Institute, Palo Alto, CA., USA, 1994.
9. Hwang · Corrosion Science · 2007 · 49 · 379710.1016/j.corsci.2007.03.040 ↗
10. J. Lumsden, Allan McIlree, in: 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Whistler, British Columbia, USA, August 19–23, 2007.
11. Copson · Corrosion · 1965 · 21 · 110.5006/0010-9312-21.1.1 ↗
12. Frye · 1987
13. Staehle · Corrosion · 2004 · 60 · 11510.5006/1.3287716 ↗
14. R.Comby, B.Flesch, F. de Keroulas, Circumferential cracking of French reactor steam generator tubes in the roll transition zones under the effect of stress corrosion, EPRI NP-7198-S, in: Proceedings of 1990 EPRI Workshop on Circumferential Cracking of steam Generator Tubes, Electric Power Research Institute, Palo Alto, CA, 1991.
15. A.R. McIlree, Purposes of workshop and review of past experience with circumferential cracking of steam generator tubes EPRI NP-7198-S, in: Proceedings of 1990 EPRI Workshop on Circumferential Cracking of steam Generator Tubes. Electric Power Research Institute, Palo Alto, CA, 1991.
16. J.A. Gorman, J.E. Harris, R.W. Staehle, K. Fruzzetti, in: Proceedings of the Eleventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, ANS, 2003, pp. 362–379.
17. A. Baum, Experimental evaluation of tube support plate crevice chemistry, in: Presented at 2001 EPRI Plant Chemistry Meeting, San Antonio, TX, Electric Power Research Institute, Palo Alto, CA, 2001.