Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 502-1 Nuclear Materials, Degradation, Radiation Effects, and Related Technology

[2C04-07] Fuel Cladding Material

Thu. Sep 6, 2018 10:50 AM - 11:55 AM Room C (B21 -B Building)

Chair:Sho Kano(Univ. of Tokyo)

+Add all to schedule

10:50 AM - 11:05 AM

[2C04] Considerations for the seismic evaluation of the fuel assembly after Loss-of-Coolant-Accident (LOCA) in PWR

(1)Result of four-point-bending tests with a fuel rod cladding exposed to the temperature condition of a postulated LOCA

*Daisuke Komiyama¹, Toshiyuki Ogita² (1. Mitsubishi Nuclear Fuel Co., Ltd, 2. The Kansai Electric Power Co., Inc.)

11:05 AM - 11:20 AM

[2C05] Considerations for the seismic evaluation of the fuel assembly after Loss-of-Coolant-Accident (LOCA) in PWR

(2)Impact behavior of a fuel grid exposed to the temperature condition of a postulated LOCA

Ryo Fukuda¹, Nozomu Murakami¹, *Masaaki Yamato¹, Hisashi Koike², Yasunari Shinohara² (1. Mitsubishi Heavy Industries, Ltd., 2. Nuclear Development Corporation)

11:20 AM - 11:35 AM

[2C06] Feasibility study of eddy current testing for accident tolerant fuel using silicon carbide in light water reactor

*Noriyasu Kobayashi¹, Jun Semboshi¹, Megumi Akimoto¹, Masaru Ukai¹ (1. Toshiba Energy Systems & Solutions)

11:35 AM - 11:50 AM

[2C07] Permeation behavior of tritium through FeCrAl-ODS ferritic steel

*Yudai Urabe¹, Kenichi Hashizume¹, Teppei Otsuka², Kan Sakamoto³ (1. Kyushu Univ., 2. Kindai Univ., 3. NFD)

Time reserved for Chair (11:50 AM - 11:55 AM)

Session information