[3P10-11] Fukushima Daiichi NPP Accident

[3P10] Analysis of core temperature increase behavior in Fukushima Daiichi NPP Unit 2 by RELAP/SCDAPSIM

*Shinji Yoshikawa¹, Ikken Sato¹ (1. Japan Atomic Energy Agency)

Keywords:Boiling Water Reactor, severe accident, Fuel Rod Cladding

The mechanism of the in-core temperature ascent in the 1st pressure peak specific to 1F2 is considered through numerical analysis with RELAP/SCDAP code