2023 Fall Meeting

Presentation information

Oral presentation

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

[3A01-05] Fuel Cladding Materials 1

Fri. Sep 8, 2023 9:30 AM - 10:55 AM Room A (IB Bildg.1F IB013)

Chair:Yoshitaka Matsukawa(Kumamoto Univ.)

10:30 AM - 10:45 AM

[3A05] Development of Cr-coated Zircaloy for Accident TolerantFuels

(5) Materials design and surface reactions of Cr by first principle calculations

*Ying Chen1, Theressa Davey1, Masatake Yamaguchi2, Akira Nakayama3, Kazuhiro Takanabe3, Hiroaki Abe3 (1. Tohoku University, 2. Japan Atomic Energy Agency, 3. The University of Tokyo)

Keywords:Accident Tolerant Fuels, Alloy design, Surface reaction, First-principles

This presentation is the 5th in a series of presentations on "Development of Cr-coated Zircaloy for Accident Tolerant Fuels". Result of Cr alloy design and chemical reaction for hydrogen generation on Cr surface based on the first-principles calculation will be presented.

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