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 language | English |
|---|---|
| Title of host publication | Thermal-Hydraulics |
| Publisher | American Society of Mechanical Engineers (ASME) |
| Volume | 6 |
| ISBN (Print) | 9784888982566 |
| DOIs | |
| Publication status | Published - 2017 |
| Event | 2017 25th International Conference on Nuclear Engineering, ICONE 2017 - Shanghai, China Duration: 2017 Jul 2 → 2017 Jul 6 |
Other
| Other | 2017 25th International Conference on Nuclear Engineering, ICONE 2017 |
|---|---|
| Country | China |
| City | Shanghai |
| Period | 17/7/2 → 17/7/6 |
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ASJC Scopus subject areas
- Nuclear Energy and Engineering
Cite this
Investigation on accident progression and melt behavior at the fukushima daiichi units 1 & 2 using melcor code. / Li, Gen; Zheng, Shan; Yamaji, Akifumi; Chong, Daotong; Yan, Junjie.
Thermal-Hydraulics. Vol. 6 American Society of Mechanical Engineers (ASME), 2017.Research output: Chapter in Book/Report/Conference proceeding › Conference contribution
}
TY - GEN
T1 - Investigation on accident progression and melt behavior at the fukushima daiichi units 1 & 2 using melcor code
AU - Li, Gen
AU - Zheng, Shan
AU - Yamaji, Akifumi
AU - Chong, Daotong
AU - Yan, Junjie
PY - 2017
Y1 - 2017
N2 - 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.
AB - 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.
UR - http://www.scopus.com/inward/record.url?scp=85032484704&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85032484704&partnerID=8YFLogxK
U2 - 10.1115/ICONE25-66389
DO - 10.1115/ICONE25-66389
M3 - Conference contribution
AN - SCOPUS:85032484704
SN - 9784888982566
VL - 6
BT - Thermal-Hydraulics
PB - American Society of Mechanical Engineers (ASME)
ER -