PWSCC susceptibility evaluation of mill annealed Alloy 600 SG tubings using mock-up specimens in lithium enhanced 360 C water
- Mitsubishi Heavy Industries, Ltd., Takasago (Japan)
- Kansai Electric Power Co., Inc., Osaka (Japan)
Intergranular stress corrosion cracking (IGSCC) behavior of Alloy 600 steam generator (SG) tubing in pressurized water reactor (PWR) primary water environments, or so called PWSCC, has been investigated since the first report by Coriou in 1959. The acceleration of PWSCC by elevating the test temperature up to 365 C, was first reported in 1980 by Bulischeck et al.. Since then, many results of PWSCC phenomena have been reported. It is important for preventive maintenance planning, to predict the life expectation at the operating temperature for a specific structural design. PWSCC susceptibility of mill annealed alloy 600 (MA 600) SG tubing was investigated using mock-up specimens, such as tube sheet expansion specimens and dent shape deformed specimens in lithium enhanced 360 C water (500ppm as B, 20ppm as Li, 45ccH{sub 2}/kgH{sub 2}O). Uniaxial constant load (UCL) tests were carried out for MA 600, thermally treated (TT) Alloy 600, and TT 690 to evaluate the effect of stress, and to evaluate the acceleration factor of the environment compared with the results in normal 360 C reactor coolant system (RCS) water (500ppm as B, 2ppm as Li, 30ccH{sub 2}/kgH{sub 2}O).
- OSTI ID:
- 203799
- Report Number(s):
- CONF-950816--; ISBN 1-877914-95-9
- Country of Publication:
- United States
- Language:
- English
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