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

    研究成果: Conference contribution

    抄録

    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.

    本文言語English
    ホスト出版物のタイトルThermal-Hydraulics
    出版社American Society of Mechanical Engineers (ASME)
    6
    ISBN(印刷版)9784888982566
    DOI
    出版ステータスPublished - 2017
    イベント2017 25th International Conference on Nuclear Engineering, ICONE 2017 - Shanghai, China
    継続期間: 2017 7 22017 7 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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