Intergranular Stress Corrosion Crack Initiation and Temperature Dependence of Alloy 600 in Pressurized Water Reactor Primary Water

Conference · Sun Apr 15 04:00:00 EDT 2018

OSTI ID:1991277

Zhai, Ziqing ^[1]; Toloczko, Mychailo B. ^[1]; Schreiber, Daniel K. ^[1]; Bruemmer, Stephen M. ^[1]

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1. BATTELLE (PACIFIC NW LAB)

Stress corrosion crack (SCC) initiation of a solution annealed, cold-worked (CW) UNS N06600 (Alloy 600) material was investigated in 360 and 325ºC simulated PWR primary water using constant load tensile instrumented for in-situ detection by the direct current potential drop technique. This CW material with high boron and low carbon bulk concentrations was found to be highly susceptible to SCC. Consistent SCC initiation times were obtained at both temperatures and the thermal activation energy for SCC initiation is estimated at ~116 kJ/mol.

• Research Organization: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-76RL01830
• OSTI ID: 1991277
• Report Number(s): PNNL-SA-129755
• Country of Publication: United States
• Language: English