2017 Annual Meeting

Presentation information

Oral presentation

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

[1I13-17] characteristics of fuel cladding

Mon. Mar 27, 2017 4:25 PM - 5:50 PM Room I (16-304 Building No.16)

Chair: Ken Kurosaki (Osaka Univ.)

5:10 PM - 5:25 PM

[1I16] The development of self-healing coating on zirconium alloy

*Zhengang Duan1, Huilong Yang2, Sho Kano2, Kenta Murakami2, Hiroaki Abe2 (1. Tohoku University, 2. The University of Tokyo)

Keywords:self-healing, coaing, cladding

The well-known inherent demerits of Zr-based alloys such as rapid oxidation and hydrogen production at high-temperature steam, especially in the case of the lost-of-coolant accident (LOCA), cannot be altered by optimizing the Zr-alloy chemical composition and/or their manufactory processes alone, which was highlighted further by the Fukushima accident.The coating technology is much more economic than substitutes for Zr-base alloys without the necessity to modify the base materials, contributing to the possibility for commercial application in the very near term. In addition, the self-healing coating, which can repair the damages automatically, or by an external trigger, is much more attractive. A new conception of self-healing coating has been proposed, and is under development.