Presentation Information
[1G10]Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR(1) Updated development road map:2025
*Yuji Okada1, Daiki Sato1, Koki Hagihara1, Yasunari Shinohara2, Shinichiro Yamashita3 (1. MHI, 2. NDC, 3. JAEA)
Keywords:
Light Water Reactor,Accident tolerance,Fuel cladding,Coating,Irradiation test
Password required to view
Log in
or
Comment
To browse or post comments, you must log in.Log in