2022 Fall Meeting

Presentation information

Oral presentation

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

[2E07-08] Corrosion

Thu. Sep 8, 2022 11:25 AM - 12:00 PM Room E (E1 Bildg.2F No.24)

Chair:Chikashi Suzuki(JAEA)

11:40 AM - 11:55 AM

[2E08] SCC initiation test of cold worked Alloy 690TT under simulated PWR primary water

Crack initiation of cavity induced specimens prior to SCC initiation test

*Toru Oumaya1, Takumi Terachi2, Takuyo Yamada1, Kohei Kokutani1, Koji Arioka1 (1. Institute of Nuclear Safety System, Incorporated, 2. The Kansai Electric Power Company, Incorporated)

Keywords:Alloy 690TT, SCC initiation test, Simulated PWR primary water, cold worked material, grain boundary cavities

SCC initiation test were conducted for cold worked Alloy 690TT in simulated PWR primary water. Blunt notched specimens that were loaded in high temperature air to form cavities on grain boudary were tested. After 220h loading in 450 deg.C and 2,269h SCC testing in 360 deg.C, small grain boundary cracks were observed on the notch tip. It was earlier than the 40,635h of SCC initation test without cavity formation. The result indicated that SCC initiation may be enhanced due to cavity formation on grain boudary prior to SCC initiation test.