Effect of long-term thermal aging on the material properties of nickel-base alloy and carbon steel welded joints

Book · Sun Dec 01 04:00:00 EST 1996

OSTI ID:403318

Takahashi, Takao; Suzuki, Isao ^[1]; Chujo, Noriyuki ^[2]; Enomoto, Kunio ^[3]; Akiyama, Mamoru ^[4]; Yoshitsugu, Mishima ^[4]

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1. Japan Power Engineering and Inspection Corp., Chiba (Japan)
2. Toshiba Corp., Yokohama (Japan)
3. Hitachi Ltd. (Japan)
4. Univ. of Tokyo (Japan)

To extend the LWR plant life, the technical basis is required to evaluate the lives of structural components with the data base of the age-related degraded material properties. In BWR plants, CRD stub tubes of RPV, and core-internals, etc. are mainly fabricated from nickel-base alloy and austenitic stainless steel, and nozzle safe-ends of RPV and reactor coolant pressure boundary piping are mainly fabricated from carbon steels. In order to evaluate the service lives of these components, it is necessary to clarify the fatigue properties and fracture toughness of the long-term thermally aged materials. The present study provides the material test results of thermally aged Alloy 600 (SB166) welded joints and carbon steel (SA508C{ell}.1) welded joints thermally aged at the aging condition equivalent to 80 year service life. The present paper mainly describes the results of the fatigue strength, fatigue crack growth in the simulated BWR water environment, fracture toughness tests, and Charpy impact test of the thermally aged Alloy 600 (SB166) and carbon steel welded joints.

• OSTI ID: 403318
• Report Number(s): CONF-960706--; ISBN 0-7918-1782-2
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
BWR TYPE REACTORS
CRACK PROPAGATION
EXPERIMENTAL DATA
FATIGUE
FRACTURE PROPERTIES
INCONEL 600
REACTOR COMPONENTS
REACTOR MATERIALS
RELIABILITY
SERVICE LIFE
STEEL-ASTM-A508
WATER CHEMISTRY
WELDED JOINTS