The accident progression and melt behavior at the Fukushima Daiichi Units 1 and 2 were investigated using MELCOR 2.1. In the modeling the lower head failure mechanism by penetration tube rupture and ejection was modeled. In the modeling of Unit 2, according to the latest findings by TEPCO investigation, the possibilities of torus room flooding, RCIC piping leakage and thermal stratification in suppression pool were taken into account. The analysis results indicate that for Unit 1 when considering penetration tube failure, a part of debris still remained in the lower head after debris discharge; otherwise all the debris discharged out. The present MELCOR modeling of Unit 2 well reproduced the RPV and PCV pressure. A part of the core was damaged and the debris that slumped into the lower head was sufficiently cooled down. The pressure vessel kept intact.
Investigation on Accident Progression and Melt Behavior at the Fukushima Daiichi Units 1 and 2 Using MELCOR Code
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Li, G, Zheng, S, Yamaji, A, Chong, D, & Yan, J. "Investigation on Accident Progression and Melt Behavior at the Fukushima Daiichi Units 1 and 2 Using MELCOR Code." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 6: Thermal-Hydraulics. Shanghai, China. July 2–6, 2017. V006T08A029. ASME. https://doi.org/10.1115/ICONE25-66389
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