Corrosion fatigue crack growth rate in sensitized alloy 600 in thiosulfate solution

Book · Tue Oct 01 04:00:00 EDT 1996

OSTI ID:367732

Kuoh, C C; Tsai, W T; Lee, J T ^[1]

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1. National Cheng Kung Univ., Tainan (Taiwan, Province of China). Dept. of Materials Science and Engineering

Alloy 600 has been widely used as the steam generation tubing material for pressurized water reactors of nuclear power generation plants. Here, the corrosion fatigue crack growth (FCG) behavior of sensitized (1,100 C/0.5h + 700 C/5h) Alloy 600 in 0.1M sodium thiosulfate solution at room temperature under applied anodic potential conditions was investigated by employing fracture mechanics technique. The results show that the FCG rate depends on the testing frequency and the potential applied. At a frequency of 1 Hz, the FCG rates were independent of the potential applied and were almost the same as that tested in N{sub 2} atmosphere. However, at a frequency of 0.1 Hz, the FCG rate increased with increasing applied potential. The fracture morphology of the corrosion fatigue of sensitized Alloy 600 was decided by the competition of environment and mechanical effect.

• OSTI ID: 367732
• Report Number(s): CONF-960389--
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
AMBIENT TEMPERATURE
CORROSION FATIGUE
CORROSIVE EFFECTS
CRACK PROPAGATION
EXPERIMENTAL DATA
INCONEL 600
PWR TYPE REACTORS
REACTOR MATERIALS
STEAM GENERATORS
THIOSULFATES