Deterministic Formulation of the Effect of Stress Intensity Factor on PWSCC of Ni-Base Alloys and Weld Metals

Author:

Lu Zhanpeng,Shoji Tetsuo1,Xue He,Fu Chaoyang2

Affiliation:

1. e-mail:

2. Fracture and Reliability Research Institute, Faculty of Engineering, Tohoku University, Aramaki Aoba 6-6-10, Aoba-ku, Sendai 980-8579, Japan

Abstract

The fundamental correlations such as crack growth rate (CGR) versus K for primary water stress corrosion cracking (PWSCC) of nickel-base alloys in simulated pressurized water reactor environments are quantified with the theoretical model based on the combination of crack tip mechanics and oxidation kinetics. Materials reliability program (MRP) proposed a CGR disposition curve in a report MRP 55 for PWSCC of thick-section Alloy 600 materials. This deterministic CGR equation has been adopted by Section XI Nonmandatory Appendix O of the ASME Boiler and Pressure Code for flaw evaluation. MRP also proposed a CGR disposition curve in a report MRP 115 for PWSCC of Alloy 82/182/132 weld metals. Stress intensity factor (K), temperature and thermal activation energy are included in both MRP 55 and MRP 115 reports. Both MRP 55 and MRP 115 are engineering-based. The results of mechanism-based modeling are compared with the screened experimental data for typical PWSCC systems of nickel-base alloys and the consistence is observed.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Reference49 articles.

1. Scott, P. M., and Benhamou, C., 2001, “An Overview of Recent Observation and Interpretation of IGSCC in Nickel base Alloys in PWR Primary Water,” Proceedings of the 10th International Conference Environmental Degradation Materials Nuclear Power Systems-Water Reactors, NACE, CDROM.

2. Scott, P. M., and Combrade, P., 2003, “On the Mechanism of Stress Corrosion Crack Initiation and Growth in Alloy 600 Exposed to PWR Primary Water,” Proceedings of the 11th International Conference Environmental Degradation of Materials Nuclear Power Systems-Water Reactors, ANS, pp. 29–35.

3. Scott, P. M., Meunier, M. C., Calonne, O., Foucault, M. P., Combrade, P., and Amzallag, C., 2007, “Comparison of Laboratory and Field Experience of PWSCC in Alloy 182 Weld Metal,” Proceedings of the 13th International Conference Environment Degradation of Materials in Nuclear Power Systems-Water Reactors, CDROM.

4. Materials Reliability Program (MRP) Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Thick-Wall Alloy 600 Materials (MRP-55NP);MRP-55NP,2002

5. White, G. A., Hickling, J., and Mathews, L. K., 2003, “Crack Growth Rates for Evaluating PWSCC of Thick-Wall Alloy 600 Material,” Proceedings of the 11th International Conference Environmental Degradation Materials Nuclear Power Systems-Water Reactors, ANS, pp. 166–179.

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