2020 Fall Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 501-2 Nuclear Fuel and the Irradiation Behavior

[1E01-07] Accident Tolerant Fuel

Wed. Sep 16, 2020 10:00 AM - 12:00 PM Room E (Zoom room 5)

Chair:Kazuo Kakiuchi(JAEA)

11:30 AM - 11:45 AM

[1E07] R&D of advanced stainless steels for BWR fuel claddings (5)

(4)Detail evaluation of oxidation behaviour

*Yoshiyuki Nemoto1, Yuki Fujimura1, Kan Sakamoto2, Shinichiro Yamashita1 (1. JAEA, 2. NFD)

Keywords:ATF, ODS, Oxidation behaviour, Oxide layer, FeCrAl-ODS alloy

FeCrAl-ODS steel is one of candidates for Accident Tolerant Fuel (ATF) cladding material. To investigate the detail oxidation behavior of the material, the authors conducted oxidation tests in high temperature steam flow in thermobalance chamber. After the tests, surface oxide layer was studied by using laser Raman spectroscopy, scanning electron microscopy and electron dispersed X-ray spectroscopy to discuss the difference of oxidation behavior at different testing temperature. At 1150C, the surface oxide layer was Alumina, and at 750C, it was Fe oxides. The detail of our investigation will be discussed in the session.