Scoring Process for Evaluating Laboratory PWSCC Crack Growth Rate Data of Thick-Wall Alloy 690 Wrought Material and Alloy 52, 152, and Variant Weld Material
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 an industry need for an equation or methodology to predict crack growth rates (CGRs) for primary water stress corrosion cracking (PWSCC) of these materials. An international PWSCC CGR Expert Panel was organized by EPRI, with the participation of national laboratories sponsored by the US NRC, 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 from seven research laboratories was compiled, evaluated and 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 process by which these data were evaluated and scored is presented in this paper.
KeywordsPWSCC Crack growth rate Expert panel Alloy 690
The authors would like to acknowledge the members of the Data Evaluation Subgroup of the Expert Panel, which developed and applied the scoring procedure discussed in this paper, in addition to providing most of the CGR data. In particular, thanks goes out to Peter Andresen (GE-GRC, now retired), Bogdan Alexandreanu (ANL), Stuart Medway (Amec Foster Wheeler), F.J. Perosanz and Lola Gomez-Briceño (CIEMAT), Denise Paraventi (Bettis, now NNL), and Mychailo Toloczko (PNNL).
- 1.Materials Reliability Program (MRP) Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Thick-Wall Alloy 600 Materials (MRP-55) Revision 1, EPRI, Palo Alto, CA: 2002. 1006695Google Scholar
- 2.G.A. White, J. Hickling, and L.K. Mathews, “Crack Growth Rates for Evaluating PWSCC of Thick-Wall Alloy 600 Material,” in Proceedings of the 11th International Conference of Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, 2003, pp. 166–179Google Scholar
- 3.Materials Reliability Program Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Alloy 82, 182, and 132 Welds (MRP-115), EPRI, Palo Alto, CA: 2004. 1006696Google Scholar
- 4.G.A. White, N.S. Nordmann, J. Hickling, and C.D. Harrington, “Development of Crack Growth Rate Disposition Curves for Primary Water Stress Corrosion Cracking (PWSCC) of Alloy 82, 182, and 132 Weldments,” in Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, 2005, pp. 511–531Google Scholar
- 5.Materials Reliability Program: Crack Growth Rates for PWSCC of Alloy 690 and Alloy 52, 152, and Variants Welds (MRP-386), EPRI, Palo Alto, CA: 2017. 3002010756Google Scholar
- 6.Models of Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Light Water Reactor Environments: Volume 1: Disposition Curves Development; Volume 2: Disposition Curves Application, EPRI, Palo Alto, CA: 2014. 3002003103Google Scholar