2017 Fall Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 405-3 Decommissioning Technology of Nuclear Facilities

[3D01-07] Evaluation for Accident Reactor

Fri. Sep 15, 2017 10:10 AM - 12:00 PM Room D (B31 - B3 Block)

Chair:Yoichi Wada (Hitachi)

10:55 AM - 11:10 AM

[3D04] Dissolution behavior of stainless steel into Fe-Cr-Ni-B-C alloy

*Jiang Liu1, Takehiro Sumita1, Yoshinao Kobayashi1 (1. Tokyo Institute of Technology)

Keywords:severe accident, fuel debris, dissolution, diffusion coefficient, stainless steel

To assess the access route to the fuel debris in nuclear power plant, corrosion condition of the structural stainless steel by the corium should be clarified. By immersion experiment, the dissolution behavior of boron and carbon into the stainless steel was estimated. Meanwhile, the influence of grain size on the dissolution behavior was indicated.