2022 Annual Meeting

Presentation information

Oral presentation

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

[2J05-08] Severe Accident 3

Thu. Mar 17, 2022 2:45 PM - 4:00 PM Room J

Chair: Teppei Otsuka (Kindai Univ.)

3:15 PM - 3:30 PM

[2J07] Initial melting reaction mechanism of BWR structural material with Zircaloy/Steel or Inconel

*Ayumi Itoh1, Shintaro Yasui Yasui1, Yoshinao Kobayashi1, Kan Sakamoto2, Kenichi Ito3, Mutsumi Hirai3, Masato Mizokami3 (1. Tokyo Tech, 2. NFD, 3. TEPCO HD)

Keywords:Fukushima Daiichi Nuclear Power Plant, Fuel bundle degradation , Zircaloy4, SUS316, Inconel718

Isothermal annealing test with diffusion couples of Zircaloy4/SUS316 and Zircaloy4/Inconel718 was performed to investigate the liquefaction mechanism which could follow the degradation BWR-type fuel bundle under severe accident conditions. The specimens after test were analyzed with SEM/EDS and powder XRD measurement to investigate the morphology and phase of reaction products.