2021 Fall Meeting

Presentation information

Oral presentation

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

[3D13-16] Zircalloy

Fri. Sep 10, 2021 4:00 PM - 5:15 PM Room D

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

4:30 PM - 4:45 PM

[3D15] Development of Metal-Coated Zircaloy for Accident Tolerant Fuel

(1)Summary and Plan of the Project

*Hiroaki Abe1, Sho Kano1, Huilong Yang1, Kazuhiro Takanabe1, Akira Nakayama1, Ying Chen2, Masatake Yamaguchi3, Yasunari Shinohara4, Koichi Ogata4 (1. The University of Tokyo, 2. Tohoku University, 3. JAEA, 4. NDC)

Keywords:accident torelant fuel, Cr coated zircaloy

A review of the project supported by MEXT, like the structure of the project and the research plan will be presented. Development of metal-coated zircaloy for accident tolerant fuel, such as materials development, corrosion behavior, anti-hydrogenation, and radiation damage will be investigated together with experimental and theoretical approaches.