Investigation on accident progression and melt behavior at the fukushima daiichi units 1 & 2 using melcor code

Gen Li, Shan Zheng, Akifumi Yamaji, Daotong Chong, Junjie Yan

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

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.

Original languageEnglish
Title of host publicationThermal-Hydraulics
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Print)9784888982566
DOIs
Publication statusPublished - 2017
Event2017 25th International Conference on Nuclear Engineering, ICONE 2017 - Shanghai, China
Duration: 2017 Jul 22017 Jul 6

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
Volume6

Other

Other2017 25th International Conference on Nuclear Engineering, ICONE 2017
CountryChina
CityShanghai
Period17/7/217/7/6

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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