2017 Annual Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 304-1 Thermal Hydraulics, Energy Conversion, Energy Transfer, Energy Storage

[2K10-15] Fukushima Daiichi NPP Accident 1

Tue. Mar 28, 2017 2:45 PM - 4:20 PM Room K (16-306 Building No.16)

Chair: Tadashi Narabayashi (Hokkaido Univ.)

3:00 PM - 3:15 PM

[2K11] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(85)Analysis of Fukushima Daiichi Unit 2 "3-peaks region" by the SAMPSON code based on the conclusions obtained from CORA-17 experiment validation

*Hector Lopez1, Marco Pellegrini1, Masanori Naitoh1 (1. IAE)

Keywords:Severe accident, Reflooding, CORA-17, "3-peak" unit 2

The main porpouse of the analysis is to understand and reproduce the behavior of the reactor during the "3-peak region" registered during the accident. It is assumed that those peaks where a consequence, in large degree of hydrogen generation caused by the core reflooding.

CORA-17 experiment has been used to develop an validate some models to predict the hydrogen generation during the reflooding process in order to aply those conclusions to the reactor analysis

The initial conclusions show a better agreement between the code and the CORA experiment, it is expetect ot observe the same improvment in the reactor