[3D13-16] Zircalloy

[3D16] Development of Metal-Coated Zircaloy for Accident Tolerant Fuel

(2)Materials Development and Radiation Effects

*Sho Kano¹, Kenta Murakami^1,2, Huilong Yang¹, Kazuhiro Takanabe¹, Akira Nakayama¹, Ying Chen³, Masataka Yamaguchi⁴, Yasunari Shinohara⁵, Koichi Ogata⁵, Hiroaki Abe¹ (1. UTokyo, 2. Nagaoka Univ. of Tech., 3. Tohoku Univ., 4. JAEA, 5. NDC)

Keywords:Accident tolerance fuel, Radiation damage, Ion irradiation

In order to clarify the irradiation integrity of the accident tolerance fuel of the light water reactor, a plate-shaped pure-Cr coating Zry4 was prepared by diffusion bonding. 320 keV-He⁺ was irradiated at ~0.5 dpa at room temperature, the microstructure observation and nano-indentation hardness testing before and after the irradiation was then conducted. As a result, the microcracks were observed at the bonding layer due to irradiation irrespective of stress loading. We will also discuss the mechanism of microcracks formation in our presentation.