2024 Annual Meeting

Presentation information

Oral presentation

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

[3C10-13] Corrosion

Thu. Mar 28, 2024 2:45 PM - 3:55 PM Room C (21Bildg.2F 21-205)

Chair:Kazunori Morishita(Kyoto Univ.)

3:00 PM - 3:15 PM

[3C11] SCC Initiation and Propagation Mechanisms of Stainless Steel in Simulated PWR primary water

(1) Investigation from Nanoscale Analysis of Crack Tip

*Katsuhiko Fujii1, Takumi Terachi1, Takuyo Yamada1, Koji Arioka1 (1. INSS)

Keywords:stainless steel, stress corrosion cracking, nanoscale analysis of crack tip, TEM, SCC initiation and propagation mechanisms

Based on the results of crack tip observation of stress corrosion cracking (SCC) that propagated in 20% cold-worked 316 stainless steel in PWR primary system simulated water at 320℃ and 360℃ using TEM and STEM/EDS, we discuss the SCC propagation mechanism.

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