2017 Fall Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 402-1 Nuclear Materials and the Irradiation Behavior

[2I01-07] Stainless Steel

Thu. Sep 14, 2017 10:05 AM - 12:00 PM Room I (C310 - C Block)

Chair:Terumitsu Miura (INSS)

11:05 AM - 11:20 AM

[2I05] Fundamental technology development for evaluation of thermally ageing embrittlement of stainless steel welds used as pressure boundaries in nuclear power plants

(2)Thermal aging behavior of stainless steel welds

*Hiroshi ABE1, Yutaka Watanabe1, Yoichi Takada1, Toshiaki Horiuchi2, Satoshi Minamoto3 (1. Tohoku University, 2. Hokkaido University of Science, 3. NIMS)

Keywords:weld metal, thermal embrittlement, austenitic stainless steels

Hardening behavior of ferrite phase in thermally aged austenitic stainless steel welds was investigated. Nanometer-scaled characterization of microstructure was also carried out to evaluate spinodal decomposition. It has been suggested that solidification mode affected age-hardening behavior of ferrite phase.