2016 Fall Meeting

Presentation information

Oral Presentation

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

[2K16-20] Fukushima Daiichi NPP Accident 2

Thu. Sep 8, 2016 4:20 PM - 5:40 PM Room K (Kumume City Plaza - Assembly Room 1)

Chair: Yoshiro Kudo (NRA)

4:20 PM - 4:35 PM

[2K16] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(82)Assessment of SAMPSON Severe Accident Code Modeling against MELCOR

*Ayumi Itoh1, Marco Pellegrini1, Hidetoshi Okada1, Masanori Naitoh1 (1.The Institute of Applied Energy)

Keywords:SAMPSON, MELCOR, UN1, Crosswalk, Severe Accident Code

The Fukushima Daiichi nuclear power plant accident is analysed by various severe accident (SA) computer codes like SAMPSON, MELCOR and MAAP, which shows different results with different initial condition or user inputs. In this study, we performed calculations against UN1 accident progression with SAMPSON and compared the results with those of MELCOR with the same initial condition. Assessment about the difference of the two codes results and where these difference come from with consideration about numerical solving approach or model difference will be presented.