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

Daisuke Komiyama

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)

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.)

Keywords:LOCA, fule cladding, coolability, seismic strength

In order to understand the fuel rod coolablity under seismic event following LOCA, maximum bending morments of fuel rod claddings after high temperature oxidation and quench were obtained by four-point-bending tests.