4:20 PM - 4:35 PM
[2C16] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR
(1) Effect of coating on a safety evaluation and updated development road map
*Daiki Sato1, Nozomu Murakami1, Yuji Okada1 (1. MHI)
Session information
Oral presentation
V. Nuclear Fuel Cycle and Nuclear Materials » 501-2 Nuclear Fuel and the Irradiation Behavior
[2C16-20] Accident Tolerant Fuel
Thu. Sep 7, 2023 4:20 PM - 5:40 PM Room C (IB Bildg.1F IB015)
Chair:Masato Kato(JAEA)
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
*Yuji Okada1, Nozomu Murakami1, Daiki Sato1, Yasunari Shinohara2, Koichi Ogata2, Shimizu Yuki2 (1. MHI, 2. NDC)
4:50 PM - 5:05 PM
*Hiroki Yokoyama1, Kan Sakamoto1, Yusuke Miura1, Nozue Mitsuo1, Shinichiro Yamashita2, Ikuo Ioka2 (1. NFD, 2. JAEA)
5:05 PM - 5:20 PM
*Chisato Sakaguchi1, Kan Sakamoto1, Yusuke Miura1, Hideyuki Kasahara2, Hajime Miyata2, Junji Matsunaga3 (1. NFD, 2. HGNE, 3. GNF-J)
5:20 PM - 5:35 PM
[2C20] Development of Fuel Performance Code RANNS for Analysis of Accident Conditions
High Temperature Oxidation Behavior of Cr-coated Accident Tolerant Fuel Cladding
*Yoshinori Taniguchi1, Yutaka Udagawa1 (1. JAEA)
Time reserved for Chair (5:35 PM - 5:40 PM)