Mechanical Properties and Corrosion Characteristics of Thermally Aged Alloy 22

Conference · Thu May 30 04:00:00 EDT 2002

DOI:https://doi.org/10.1115/PVP2002-1621· OSTI ID:15013566

Rebak, R B; Crook, P

Alloy 22 (UNS N06022) is a candidate material for the external wall of the high level nuclear waste containers for the potential repository site at Yucca Mountain. In the mill-annealed (MA) condition, Alloy 22 is a single face centered cubic phase. When exposed to temperatures on the order of 600 C and above for times higher than 1 h, this alloy may develop secondary phases that reduce its mechanical toughness and corrosion resistance. The objective of this work was to age Alloy 22 at temperatures between 482 C and 760 C for times between 0.25 h and 6,000 h and to study the mechanical and corrosion performance of the resulting material. Aging was carried out using wrought specimens as well as gas tungsten arc welded (GTAW) specimens. Mechanical and corrosion testing was carried out using ASTM standards. Results show-that the higher the aging temperature and the longer the aging time, the lower the impact toughness of the aged material and the lower its corrosion resistance. However, extrapolating both mechanical and corrosion laboratory data predicts that Alloy 22 will remain corrosion resistant and mechanically robust for the projected lifetime of the waste container.

• Research Organization: Lawrence Livermore National Laboratory (LLNL), Livermore, CA
• Sponsoring Organization: USDOE
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 15013566
• Report Number(s): UCRL-JC-148653
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
AGING
CONTAINERS
CORROSION RESISTANCE
FCC LATTICES
HASTELLOYS
HIGH-LEVEL RADIOACTIVE WASTES
MATERIALS TESTING
MECHANICAL PROPERTIES
RADIOACTIVE WASTE DISPOSAL
YUCCA MOUNTAIN