Characterization of the Resistance of Alloy 22 to Stress Corrosion Cracking

Conference · Thu May 30 00:00:00 EDT 2002

DOI:https://doi.org/10.1115/PVP2002-1620· OSTI ID:15013493

King, K J; Estill, J C; Rebak, R B

In its current design, the high-level nuclear waste containers include an external layer of Alloy 22 (Ni-22Cr-13Mo-3W-3Fe). Since over their lifetime, the containers may be exposed to multi-ionic aqueous environments, a potential degradation mode of the outer layer could be environmentally assisted cracking (EAC). The objective of the current research was to characterize the effect of applied potential and temperature on the susceptibility of Alloy 22 to EAC in simulated concentrated water (SCW) using the slow strain rate test (SSRT). Results show that Alloy 22 may suffer EAC at applied potentials approximately 400 mV more anodic than the corrosion potential (E{sub corr}).

• Research Organization: Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 15013493
• Report Number(s): UCRL-JC-147912; TRN: US0600166
• Resource Relation: Journal Volume: 2002; Conference: American Society of Mechanical Engineers Pressure Vessels and Piping Conference, Vancouver, Canada, Aug 04 - Aug 08, 2008
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
42 ENGINEERING
ALLOYS
CONTAINERS
CORROSION
DESIGN
ENGINEERS
LIFETIME
PRESSURE VESSELS
RADIOACTIVE WASTES
STRAIN RATE
STRESS CORROSION
WATER