2022 Annual Meeting

Presentation information

Oral presentation

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

[2J01-04] Corrosion and Diffusion

Thu. Mar 17, 2022 10:45 AM - 12:00 PM Room J

Chair: Kinya Nakamura (CRIEPI)

11:00 AM - 11:15 AM

[2J02] Effects of Temperature and Thermal Aging on SCC Behaviors of Stainless Steel Welds in Oxygenated High-Temperature Water

*Takuyo Yamada1, Toru Ooumaya1, Kohei Kokutani1, Koji Arioka1 (1. INSS)

Keywords:Stainless steel weld, SCC growth rate in high temperature water, Temperature dependence, Effect of thermal aging, Effect of water chemistry

To investigate effect of temperature and thermal aging on SCC behaviors of stainless steel welds, SCC growth measurement were performed in oxygenated high temperature water with 2900 ppm B. As a result, temperature dependence of the 316L weld was indicated Arrhenius type. And the SCC growth rate was increased after aged at 400℃x20kh.