2022 Annual Meeting

Presentation information

Oral presentation

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

[2J05-08] Severe Accident 3

Thu. Mar 17, 2022 2:45 PM - 4:00 PM Room J

Chair: Teppei Otsuka (Kindai Univ.)

3:30 PM - 3:45 PM

[2J08] Study for the seismic evaluation of the fuel assembly after Loss-Of-Coolant-Accident (LOCA) in PWR

Fabrication of LOCA simulated high temperature oxidization apparatus for full-size fuel grid

*Daisuke Komiyama1, Daiki Sato1, Takashi Oka2, Masataka Tajimi2, Koichi Ogata3, Masaaki Yamato4, Nozomu Murakami4 (1. MNF, 2. KEPCO, 3. NDC, 4. MHI)

Keywords:LOCA, coolability, seismic strength, grid, oxidation

In order to consider the maintenance of fuel coolability against earthquake after LOCA, the mechanical properties of the grid which exposed to high temperature steam atmosphere during LOCA are required. The mechanical properties of full size grid are obtained by impact testing using the full size grid. For this reason, a test apparatus for high-temperature oxidation simulating LOCA was constructed for a full-size grid, and its performance was confirmed.