2018 Fall Meeting

Presentation information

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)

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)

Keywords:LOCA, Fuel grid, coolability, Seismic evaluation

The partial grid samples were heated under the temperature and steam which postulated LOCA, and the impact testing were conducted using the partial grid samples. As a result of the testing, the structures were maintained to achieve the long term core cooling after LOCA.