NDLI: Crack Growth Rates for Evaluating PWSCC of Thick-Wall Alloy 690 Material and Alloy 52, 152, and Variant Welds

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Amanda, R. Jenks Glenn, A. White Crooker, Paul
Copyright Year	2017
Abstract	Due to the widespread use of thick-wall Alloy 690 and its corresponding weld metals Alloys 52 and 152 in various replacement, repair, mitigation, and new plant pressurized water reactor (PWR) applications, there is a need in the industry for an equation or methodology for predicting crack growth rates (CGRs) for primary water stress corrosion cracking (PWSCC) of these materials. Although there have been no indications of PWSCC reported in these materials in PWRs to date, there is the possibility that such an indication could be reported in the future or the possibility that a manufacturing defect could be conservatively interpreted as PWSCC. Crack growth rates are thus needed to support leaving such an indication in service for a justified period of time. In addition, safety assessments of hypothetical PWSCC flaws require prediction of PWSCC crack growth rates for these materials, so as to set appropriate inspection intervals. Current inspection intervals were selected to be conservative pending a consensus CGR model. Example applications for which PWSCC CGRs are needed to determine appropriate reexamination intervals include Alloy 690 penetration nozzles attached to the inside of the reactor pressure vessel top head with Alloy 52/152/variant welds, and Alloy 52/152/variant weld inlays and onlays used to mitigate Alloy 82/182 piping butt welds. An international PWSCC CGR Expert Panel was organized by EPRI, with the participation of national laboratories sponsored by the US Nuclear Regulatory Commission (NRC),1 to support the development of such PWSCC CGR equations. A database of over 500 Alloy 690 CGR data points and over 130 Alloy 52/152 CGR data points using thick-wall compact tension specimens from seven research laboratories was compiled, scored for data quality, and assessed to determine the effects of numerous parameters such as temperature, crack-tip stress intensity factor, yield strength, and crack orientation. The methodology and results of these statistical analyses are presented in this paper. It should be noted that this paper provides a status of the ongoing work, which is planned for completion in late 2017.
Sponsorship	Pressure Vessels and Piping Division
File Format	PDF
ISBN	9780791858004
DOI	10.1115/PVP2017-65886
Volume Number	Volume 6B: Materials and Fabrication
Conference Proceedings	ASME 2017 Pressure Vessels and Piping Conference
Language	English
Publisher Date	2017-07-16
Publisher Place	Waikoloa, Hawaii, USA
Access Restriction	Subscribed
Subject Keyword	Water Temperature Reactor vessels Statistical analysis Metals Alloys Inspection Fracture (materials) Maintenance Stress corrosion cracking Stress Welded joints Databases Nozzles Yield strength Tension Manufacturing Safety Pressurized water reactors Pipes
Content Type	Text
Resource Type	Article

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