2018 Fall Meeting

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Oral presentation

IV. Nuclear Plant Technologies » 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

[3P10-11] Fukushima Daiichi NPP Accident

Fri. Sep 7, 2018 2:45 PM - 3:15 PM Room P (E21 -E Building)

Chair:Masao Chaki(IAE)

2:45 PM - 3:00 PM

[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