3:00 PM - 3:15 PM
[2D02] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR
(1) Intermediate review on a reactor safety evaluation and updated development road map
Keywords:Light Water Reactor, Accident Tolerant, Fuel Cladding, Coating, Corrosion resistance
Development of the accident tolerant fuel cladding (coated zirconium alloy tube) has been progressing for implementation to PWR fleets in 2030s.
In this presentation, an intermediate technical review on currently obtained performance test results of Cr coated cladding under accident and normal operation conditions, is reported. Then outlook for performances of the Cr-coated cladding is presented.
In addition, updated the development roadmap, including topic of the irradiation test plan in a test reactor, is showed and discussed.
In this presentation, an intermediate technical review on currently obtained performance test results of Cr coated cladding under accident and normal operation conditions, is reported. Then outlook for performances of the Cr-coated cladding is presented.
In addition, updated the development roadmap, including topic of the irradiation test plan in a test reactor, is showed and discussed.