Kazuo Kakiuchi

Effect of Cr-coating for cladding tube on fuel behavior during a reactivity-initiated accident 

日本原子力学会2025年春の年会

Irradiation growth behaviour in zirconium-based alloy claddings for PWR 

Enlarged Halden Programme Group meeting, The OECD Halden Reactor Projects (HRP) final conference, Celebrating 65 years of safety research (EHPG2024)

Irradiation growth behavior in zirconium-based alloy claddings for PWR 

6th Asian Zirconium Workshop (AZW)

Evaluation of the behavior of FeCrAl-ODS cladding tube during loss-of-coolant accident 

事故耐性燃料開発に関するワークショップ

Analysis of smear samples at Unit 2 reactor building of Fukushima Daiichi NPS 

日本原子力学会2022年秋の大会

Study on the failure behavior of high-burnup fuels under reactivity initiated accident conditions (Analyses of the failure mode change observed on a PWR-MOX fuel and its occurrence condition) 

日本原子力学会2022年秋の大会

Evaluation of mechanical properties of fuel cladding tubes using nanoindentation 

令和3年度原子力規制庁技術基盤グループ-原子力機構安全研究・防災支援部門合同研究成果報告会

Overview of research activities of the Fuel Safety Research Group 

令和3年度原子力規制庁技術基盤グループ-原子力機構安全研究・防災支援部門合同研究成果報告会

Evaluation of mechanical properties of fuel cladding tubes using nanoindentation 

日本原子力学会2021年秋の大会