[2C16-20] Accident Tolerant Fuel

[2C16] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR

(1) Effect of coating on a safety evaluation and updated development road map

*Daiki Sato¹, Nozomu Murakami¹, Yuji Okada¹ (1. MHI)

Keywords:Light Water Reactor, Accident Tolerant, Fuel Cladding Tube, Coating, Irradiation Test

Cr-coated cladding as an accident tolerant fuel have been developed. Aming to check effects of Cr coating on safety evaluation using Zr alloy cadding tubes with 10 microns thickness Cr coating, the creep rate and the burst temperature of the tubes in high temperature condition were performed. In addition, irradiation test of fuel rods in a test reactor was started in order to evaluate Cr-coated cladding behaviour.