2017 Fall Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 402-1 Nuclear Materials and the Irradiation Behavior

[1I15-20] Corrosion Behavior

Wed. Sep 13, 2017 4:25 PM - 6:05 PM Room I (C310 - C Block)

Chair:Hiroaki Abe (Univ. of Tokyo)

4:25 PM - 4:40 PM

[1I15] Fundamental study on corrosion characteristics of wire-wrapped fuel cladding in lead-bismuth eutectic

*Yuhei Nakabo1, Annette Heinzel2, Alfons Weisenburger2, Minoru Takahashi3, Masatoshi Kondo3 (1. Tokyo Institute of Technology, 2. Karlsruhe Institute of Technology, 3. Laboratory for Nuclear Energy)

Keywords:Corrosion, Lead-bismuth eutectic (LBE), Accelerator driven system (ADS), Fretting

MHRRHA project aims to build accelerator driven system (ADS)with wire wrapped fuel cladding. We make clear corrosion behaivers accompanied by wire spacer. After candidate materials immersed in lead-bismuth eutectic (LBE), we investigate microstructure using SEM.