Radiation response of an yttria-based interdiffusion barrier layer for the Cr-coated ATF cladding

The Fukushima Daiichi event in 2011 demonstrated the need for improved nuclear energy safety, which can be ensured by developing accident-tolerant fuels (ATFs). ATFs must overcome the inherent technical shortcomings of zircaloy/UO2 fuels, thus relieving the industry from the financial penalties of beyond-design-basis accidents whilst protecting Society and Environment. The near-term ATF cladding material concept proposed by Westinghouse is the Cr-coated zircaloy, the reliable operation of which is limited by the Cr-Zr eutectic at 1332°C. This project studies the radiation response of an yttria-based interdiffusion barrier layer, which could potentially extend the operational ‘window’ of the Cr-coated cladding to 1500°C.