Presentation Information
[1G11]Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR(2) Interaction between Cr-coated cladding tube and spacer grid materials under high temperature steam conditions
*Koki Hagihara1, Yuji Okada1, Daiki Sato1, Yasunari Shinohara2, Shunsuke Asai2 (1. Mitsubishi Heavy Industries, Ltd., 2. MHI Nuclear Development Corporation)
Keywords:
light water reactor,Accident Tolerant,fuel cladding,Cr-coated,LOCA
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