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Stress Corrosion Cracking (SCC) models are important for engineering and regulatory assessments. The SCC time to the growth of a crack of engineering scale is the main fraction of component life prior to failure and is therefore of significant interest for modeling. However, the stochastic characteristics of early crack development is challenging for model development and validation.
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Determining the resistance of high-Cr Ni-base Alloy 690 to environmental degradation during long-term pressurized water reactor (PWR) exposure is needed to confirm its viability as the replacement material for Alloy 600 and help establish a quantitative factor of improvement for stress corrosion crack (SCC) initiation. SCC initiation testing on cold-worked (CW) Alloy 600 materials in PWR primary water has demonstrated that intergranular (IG) attack is the precursor to SCC initiation in this material. In comparison, an equivalent degradation and cracking process does not exist in CW Alloy 690.
Austenitic and ferritic-martensitic steel were irradiated with protons while exposed to simulated PWR primary water for 4-72 hr in 320°C water with 3 wppm hydrogen while irradiated at surface dose rates from 400-4000 kGy/s (4x10-7 to 7x10-6 dpa/s).
Stress corrosion crack (SCC) initiation testing has been performed on a 15% cold-worked UNS N06600 (Alloy 600) heat in mill-annealed (MA), solution annealed (SA), and thermally treated (TT) conditions to assess the role of grain boundary (GB) carbides on stress-assisted intergranular attack (IGA) and short crack nucleation and growth. The SCC initiation tests were conducted at a constant load equivalent to the materials’ yield stress in 360oC simulated pressurized water reactor primary water. Results revealed the highest SCC initiation susceptibility occurred in the Alloy 600 MA material, followed by the TT and SA materials, suggesting that GB carbide distribution did not have a controlling effect on SCC initiation resistance. Quantitative assessments of IGA and short cracks were conducted to help understand this phenomenon, and the role of GB carbides in precursor damage development that leads to differences in macroscopic SCC initiation behavior are discussed.
Environmentally-assisted cracking (EAC) of nickel-base alloys has been observed in the primary coolant of light water reactors (LWRs). One of the main issues is primary water stress corrosion cracking (PWSCC) of Alloy 182 which has been a concern for a long time. For assumed or existing defects, disposition curves (crack growth rate as function of stress intensity factor) are available.