2018 Fall Meeting

Presentation information

Oral presentation

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

[1C01-03] Severe Accident 1

Wed. Sep 5, 2018 10:00 AM - 10:50 AM Room C (B21 -B Building)

Chair:Ken-Ichi Fukumoto(Univ. of Fukui)

10:00 AM - 10:15 AM

[1C01] Melting behavior of reactor core during severe accident of BWR

(1) Fracture behavior of stainless structure materials by molten metallic and oxidic corium

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

Keywords:Severe accident, Fuel debris retrieval, Eutectic melt, Reactor materials, Stainless steel

This study aims to evaluate the fracture behavior of solid stainless steel (SS) by molten corium such as SS-B4C metallic corium, originated from control rod, and UO2-Zircaloy oxidic corium, originated from fuel rod. Immersion tests of SS rod with molten SS-B4C melt and molten UO2-Zr(O) melt were carried out.

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