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)
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

出版物シリーズ

名前International Conference on Nuclear Engineering, Proceedings, ICONE
6

Other

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

ASJC Scopus subject areas

  • 原子力エネルギーおよび原子力工学

フィンガープリント

「Investigation on accident progression and melt behavior at the fukushima daiichi units 1 & 2 using melcor code」の研究トピックを掘り下げます。これらがまとまってユニークなフィンガープリントを構成します。

引用スタイル