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http://dx.doi.org/10.5516/NET.07.2012.090

A REVIEW ON THE ODSCC OF STEAM GENERATOR TUBES IN KOREAN NPPS  

Chung, Hansub (Central Research Institute, Korea Hydro Nuclear Power)
Kim, Hong-Deok (Central Research Institute, Korea Hydro Nuclear Power)
Oh, Seungjin (Central Research Institute, Korea Hydro Nuclear Power)
Boo, Myung Hwan (Central Research Institute, Korea Hydro Nuclear Power)
Na, Kyung-Hwan (Central Research Institute, Korea Hydro Nuclear Power)
Yun, Eunsup (Central Research Institute, Korea Hydro Nuclear Power)
Kang, Yong-Seok (Central Research Institute, Korea Hydro Nuclear Power)
Kim, Wang-Bae (Central Research Institute, Korea Hydro Nuclear Power)
Lee, Jae Gon (Central Research Institute, Korea Hydro Nuclear Power)
Kim, Dong-Jin (Nuclear Gaterials Research Division, Korea Atomic Energy Research Institute)
Kim, Hong Pyo (Nuclear Gaterials Research Division, Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.45, no.4, 2013 , pp. 513-522 More about this Journal
Abstract
The ODSCC detected in the TSP position of Ulchin 3&4 SGs are typical ODSCC of Alloy 600MA tubes. The causative chemical environment is formed by concentration of impurities inside the occluded region formed by the tube surface, egg crate strips, and sludge deposit there. Most cracks are detected at or near the line contacts between the tube surface and the egg crate strips. The region of dense crack population, as defined as between $4^{th}$ and $9^{th}$ TSPs, and near the center of hot leg hemisphere plane, coincided well with the region of preferential sludge deposition as defined by thermal hydraulics calculation using SGAP computer code. The cracks developed homogeneously in a wide range of SGs, so that the number of cracks detected each outage increased very rapidly since the first detection in the $8^{th}$ refueling outage. The root cause assessment focused on investigation of the difference in microstructure and manufacturing residual stress in order to reveal the cause of different susceptibilities to ODSCC among identical six units. The manufacturing residual stress as measured by XRD on OD surface and by split tube method indicated that the high residual stress of Alloy 600MA tube played a critical role in developing ODSCC. The level of residual stress showed substantial variations among the six units depending on details of straightening and OD grinding processes. Youngwang 3&4 tubes are less susceptible to ODSCC than U3 and U4 tubes because semi-continuous coarse chromium carbides are formed along the grain boundary of Y3&4 tubes, while there are finer less continuous chromium carbides in U3 and U4. The different carbide morphology is caused by the difference in cooling rate after mill anneal. There is a possibility that high chromium content in the Y3&4 tubes, still within the allowable range of Alloy 600, has made some contribution to the improved resistance to ODSCC. It is anticipated that ODSCC in Y5&6 SGs will be retarded more considerably than U3 SGs since the manufacturing residual stress in Y5&6 tubes is substantially lower than in U3 tubes, while the microstructure is similar with each other.
Keywords
SG; Tube; ODSCC; Microstructure; Residual Stress; Sludge; Alloy 600(HT)MA;
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