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[2D07] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR
(1)Coated cladding performance at accident conditions
Keywords:LWR, Accident Tolerant, Fuel cladding, Coating
Development of an accident tolerant fuel cladding (coated zirconium alloy tube) for PWRs has started in 2019. In this paper, the performance test data of Cr coated zirconium alloy cladding under accident condition, and expected accident tolerant effect are reported.
Cr-coated cladding did not split/break due to thermal shock during quenching even after the cladding experienced temperatures above 1300 °C. This result indicates that the possibility of maintaining coolable geometry of reactor core after the cladding experienced higher temperature exceeding the current regulatory standards.
Cr-coated cladding did not split/break due to thermal shock during quenching even after the cladding experienced temperatures above 1300 °C. This result indicates that the possibility of maintaining coolable geometry of reactor core after the cladding experienced higher temperature exceeding the current regulatory standards.