Assessment of dust dispersion data for future safety analysis of Fukushima Daiichi fuel debris retrieval, 24; Small-scale fabrication and characterization of as-melted fuel debris pieces containing uranium

Takano, Masahide ; Sudo, Ayako ; Nakamura, Kinya*; Koyama, Tadafumi*; Uozumi, Koichi*; Kanai, Taizo*; Kanagawa, Shun*; Iwata, Yuichi*; Totsuka, Fumio*; Mogi, Kazutaka*; Yamauchi, Daisuke*; Honda, Takeshi*

Simulated fuel debris in RPV and CV containing uranium were fabricated by light-concentrating heating technique, respectively, to provide them for cutting tests with disc cutter. Characteristic data such as bulk density, microstructure, formed phases and micro-hardness on cross-section were obtained.

Language	:	Japanese
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Meeting title	:	日本原子力学会2025年秋の大会
Held date	:	2025/09
Location (city)	:	北九州
Location (country)	:	日本
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Keywords	:	福島第一原子力発電所事故; Fukushima Daiichi Nuclear Power Station Accident; 燃料デブリ; 圧力容器; 格納容器; 集光加熱; 特性評価
Research Facility	:	第4研究棟
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Cooperating Institute	:	電力中央研究所

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Registration No. : BB20250461
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