SCC of Alloy 690 and its Weld Metals

Author:

Andresen Peter L.,Morra Martin M.,Ahluwalia Kawaljit

Publisher

Springer International Publishing

Reference39 articles.

1. P.L. Andresen, “Perspective and Direction of Stress Corrosion Cracking in Hot Water”, Proc. Tenth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, NACE, 2001.

2. P.L. Andresen, T.M. Angeliu and L.M. Young, “Immunity, Thresholds, and Other SCC Fiction”, Proc. Staehle Symp. on Chemistry and Electrochemistry of Corrosion and SCC, TMS, Feb. 2001.

3. P.L. Andresen, L.M. Young, P.W. Emigh and R.M. Horn, “Stress Corrosion Crack Growth Rate Behavior of Ni Alloys 182 and 600 in High Temperature Water”, Corrosion/02, Paper 02510, NACE, 2002.

4. P.L. Andresen, “Conceptual Similarities and Common Predictive Approaches for SCC in High Temperature Water Systems”, Paper 96258, Corrosion/96, NACE, 1996.

5. F.P. Ford and P.L. Andresen, “Corrosion in Nuclear Systems: Environmentally Assisted Cracking in Light Water Reactors”, in “Corrosion Mechanisms”, Ed. P. Marcus and J. Ouder, Marcel Dekker, p.501–546, 1994.

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3. SCC of Alloy 152/52 Welds Defects, Repairs and Dilution Zones in PWR Water;The Minerals, Metals & Materials Series;2017-10-07

4. High-Resolution Characterizations of Grain Boundary Damage and Stress Corrosion Cracks in Cold-Rolled Alloy 690;15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors;2012-06-26

5. SCC of High CR Alloys in BWR Environments;15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors;2012-06-26

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