[3D01-07] Evaluation for Accident Reactor

[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.