The development of self-healing coating on zirconium alloy for light water reactors

Zhengang Duan

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 401-2 Nuclear Fuel and the Irradiation Behavior

[3D10-13] Fuel Cladding

Wed. Mar 28, 2018 2:45 PM - 3:55 PM Room D (R1-212 -R1 Building)

Chair: Masayoshi Uno (Univ. of Fukui)

3:00 PM - 3:15 PM

[3D11] The development of self-healing coating on zirconium alloy for light water reactors

*Zhengang Duan¹, Huilong Yang², Sho Kano², Jingjie Shen², Zishou Zhao², John McGrady², Hiroaki Abe² (1. Tohoku University, 2. The University of Tokyo)

Keywords:Self-healing, Coating, Cladding

A new self-healing concept was proposed for the fuel cladding. The feasibility of the self-healing reactions and the stability of the candidate materials have been assessed by means of the autoclave and furnace experiments.