Irradiation Assisted Stress Corrosion Cracking Susceptibility of Alloy X-750 Exposed to BWR Environments
The effect of irradiation on stress corrosion cracking susceptibility and fracture toughness of alloy X-750 has been investigated. The material has been irradiated at a target temperature of 288 ℃ in the Advanced Test Reactor at Idaho National Laboratory to a fluence of approximately 1.93 × 1020 n/cm2 (E >1 meV). Stress corrosion cracking crack growth rates were determined in both unirradiated and irradiated materials in normal water chemistry and hydrogen water chemistry environments. Although the effect of irradiation on tensile properties and fracture toughness was observed, there was no significant effect of irradiation observed on the propagation rate of stress corrosion cracks.
This work was supported under a Cooperative Research and Development Agreement between the Idaho National Laboratory (under the Nuclear Science User Facilities) and the Electric Power Research Institute.
- 1.P.L. Andresen, J. Flores-Preciado, M. Morra, R. Carter, Microstructure and SCC of Alloy X-750. in 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water reactors, 2011Google Scholar
- 2.P.L. Andresen, The Effects of Aqueous Impurities on Intergranular Stress Corrosion Cracking of Sensitized Type 304 Stainless Steel. Final Report NP3384 Contract T115-3, EPRI, 1983Google Scholar
- 4.Standard test method for measurement of fracture toughness. ASTM E 1820–09. (ASTM International, West Conshohocken, PA, 2009)Google Scholar
- 5.Standard Test Methods for Tension Testing of Metallic Materials. ASTM E 8–04. (ASTM International, West Conshohocken, PA, 2004Google Scholar
- 6.BWRVIP-240: BWR Vessels and Internals Project, Metallurgical Analyses and Macro and Microstructural Mapping of Alloy X-750 and Alloy XM-19 Plates. (EPRI, Palo Alto, CA, 2010). 1021003Google Scholar