Applicability of Alloy 690/52/152 Crack Growth Testing Conditions to Plant Components
A great deal of PWSCC testing has been conducted on a range of A690 materials. An expert panel organized by EPRI is working to collect all the available laboratory data for its applicability to actual plant components. This paper will review the considerations that are being used to perform this evaluation, and the results of that evaluation. One of the key variables is cold work, and detailed studies have been conducted to measure the residual strains, so as to determine the amount of cold work that can exist in a heat-affected-zone (HAZ) region of a typical weld. In addition to these measurements on weldments, limitations on bulk cold work on base metal imposed by all vendors will be reviewed. The effect of the orientation of the specimens tested will be compared with the orientations of typical flaws in operating plants, so as to determine the relevance of the data to those plants.
KeywordsAlloy 690 Alloy 152 Alloy 52 PWSCC Cold work Orientation
Valuable contributions to this work were obtained from Martin Morra and Peter Andresen of GE Global Research, Mike Burke and Dave Love of Westinghouse, and Peter Scott. The authors also wish to acknowledge the contributions of other members of the Alloy 690 Applications Expert Panel: Amanda Jenks, Pal Efsing, Dave Morton, and Toshio Yonezawa. This work was sponsored by the Electric Power Research Institute.
- 1.S.M. Bruemmer et al, Cold-work effects on stress corrosion crack growth in alloy 690 tubing and plate materials, in Proceedings, 17th Conference on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, August 2015Google Scholar
- 2.ASME Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Power Plants, ASME International, New York, NYGoogle Scholar
- 3.T.M. Angeliu et al, Intergranular stress corrosion cracking of unsensitized stainless steels in BWR environments, in Proceedings, 9th Conference on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, August 1999Google Scholar
- 4.Alloy 690 procurement specification, Rev. 1, Electric Power Research Institute, Palo Alto, CA, report 1026723, 2012Google Scholar
- 5.P.L. Andresen, M.M. Morra, K. Ahluwalia, SCC of alloy 690 and its weld metals, Corrosion 2012, Paper C2012-0001187, NACE International, 2012Google Scholar
- 6.Martin M. Mora, M. Othon, Weld Slice DDC-52-LAS-2: 52 M Repair/52 M Weld Interfaces, Alloy 690/52/152 PWSCC Research Collaboration Meeting (Tampa, FL, 2016)Google Scholar