2020 Annual Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 502-1 Nuclear Materials, Degradation, Radiation Effects, and Related Technology

[2M01-03] Corrosion

Tue. Mar 17, 2020 10:00 AM - 10:50 AM Room M (Lecture Bildg. S 3F S-31)

Chair:Tatsuya Hinoki(Kyoto Univ.)

10:15 AM - 10:30 AM

[2M02] Influence of Water Chemistry and Test Temperature on SCC Growth Behavior of Welds and Cast Stainless Steels in Oxygenated High-Temperature Water

*Takuyo Yamada1, Takumi Terachi1, Makie Okamoto2, Koji Arioka1 (1. INSS, 2. Kobe Material Testing Laboratory Group)

Keywords:Stainless steel weld, Cast austenitic stainless steel, SCC growth behavior in high-Temperature water, Influence of water chemistry, Temperature dependence

SCC growth behaviors of welds and cast stainless steels were investigated in oxygenated water with 2900ppmB at 320℃ and 290℃. In the case of 316L/308L welds, the temperature dependence were indicated simple 1/T, higher SCC growth rates were observed than that of the oxygenated water at 320℃ with 500ppmB + 2ppmLi.