[2D01-05] ATF, Irradiation Behavior of Water Reactor Fuel

[2D03] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR

(2) High temperature oxidation and corrosion behaviour

*Yuji Okada¹, Daiki Sato¹, Nozomu Murakami², Yasunari Shinohara³, Koichi Ogata³ (1. MNF, 2. MHI, 3. NDC)

Keywords:Light water reactor, Accident tolerance, Fuel cladding, Coating, Oxidation resistance

We continue to develop Cr-coated cladding as an accident tolerant fuel cladding. In order to investigate the oxidation resistance in accidental condition and the corrosion resistance in normal operation, the high temperature oxidation test and the corrosion test under the simulated reactor water condition were performed for the Cr-coated cladding tube. The test results show the weight gain of zirconium substrate due to high temperature oxidation and corrosion was suppressed compared with uncoated cladding tube. Based on these results, the resistance of oxidation reaction under both simulated accidental conditions and normal operation is improved by Cr coating.