Effect of long-term thermal aging on the material properties of austenitic stainless steel welded joints

Book · Sun Sep 01 04:00:00 EDT 1996

OSTI ID:277809

Asano, Masayuki ^[1]; Hattori, Shigeo ^[2]; Suzuki, Isao; Oishi, Masayuki; Koyama, Masakuni ^[3]; Akiyama, Mamoru ^[4]; Okubo, Tadatune ^[5]; Mishima, Yoshitugu ^[6]

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1. Toshiba Corp., Yokohama (Japan)
2. Hitachi Ltd., Ibaraki (Japan)
3. Japan Power Engineering and Inspection Corp., Urayasu, Chiba (Japan)
4. Tokyo Univ., Hongo, Tokyo (Japan)
5. Sophia Univ., Tokyo (Japan)
6. Tokyo Univ., Shinbashi, Tokyo (Japan)

In the light water reactor (LWR) plants, austenitic stainless steel is used in the major components such as the safe end of RPV and core-internals and so on. For the LWR plant life extension (PLEX), it is necessary to evaluate the remaining life of components based on the fatigue properties and fracture toughness of long-term aged materials. The present study provides the material test results of thermally aged Type 304 welded joints and the case study on the assessment of the structural integrity of the component based on the obtained material data. The thermal aging condition is selected to simulate that for 80 years service of a BWR plant.

• OSTI ID: 277809
• Report Number(s): CONF-960306--; ISBN 0-7918-1226-X
• 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
MATERIALS TESTING
MECHANICAL PROPERTIES
MICROSTRUCTURE
REACTOR COMPONENTS
REACTOR MATERIALS
RELIABILITY
STAINLESS STEEL-304
TENSILE PROPERTIES
WELDED JOINTS