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)

10:40 AM - 10:55 AM

[3D03] Investigation on the Fracture Behavior of Core Structure Materials by Molten Corium in Boiling Water Reactor Plants during Severe Accidents

Fracture Mode of Stainless Steel by molten Fe-Cr-Ni-B-C

*Takehiro Sumita1, Yoshinao Kobayashi1, Shigeru Ueda2, Toshio Nakagiri3 (1. Tokyo Institute of Technology, 2. Tohoku University, 3. JAEA)

Keywords:Severe accident, Fuel debri retrieval, Reactor materials, Diffusion coefficient, Stainless steel

In order to predict the damage condition of reactor vessel during severe accident at Fukushima Daiichi Nuclear Power Plant, immersion tests of stainless steel (SUS 304) rod with molten metal (SUS 304 + B4C) originated from control rod were carried out, specifically aimed to investigate the fracture behavior of core structure materials by molten corium.