4:35 PM - 4:50 PM
[2C17] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR
(2) Effect of coating on a performance under normal operation
Keywords:Light water reactor, Accident torelance, Fuel cladding, Coating
We continue to develop Cr-coated cladding as an accident tolerant fuel cladding. In order to investigate the corrosion resistance in normal operation, the corrosion test under the simulated reactor water condition were performed for the as-fabricated and the artificially defective Cr-coated cladding tube. The test results show the weight gain of zirconium substrate due to corrosion was suppressed even if the corrosion period is extended. In addition, the weight gain of substrate was not accelerated by the cracks generated in the Cr layer.
Abstract password authentication.
Password is required to view the abstract. Please enter a password to authenticate.