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)
    Volume6
    ISBN (Print)9784888982566
    DOIs
    Publication statusPublished - 2017
    Event2017 25th International Conference on Nuclear Engineering, ICONE 2017 - Shanghai, China
    Duration: 2017 Jul 22017 Jul 6

    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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  • Cite this

    Li, G., Zheng, S., Yamaji, A., Chong, D., & Yan, J. (2017). Investigation on accident progression and melt behavior at the fukushima daiichi units 1 & 2 using melcor code. In Thermal-Hydraulics (Vol. 6). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/ICONE25-66389