Fukushima Daiichi Unit 1 ex-vessel prediction: Core melt spreading
Abstract
Lower head failure and corium-concrete interaction were predicted to occur at Fukushima Daiichi Unit 1 (1F1) by several different system-level code analyses, including MELCOR v2.1 and MAAP5. Although these codes capture a wide range of accident phenomena, they do not contain detailed models for ex-vessel core melt behavior. However, specialized codes exist for analysis of ex-vessel melt spreading (e.g., MELTSPREAD) and long-term debris coolability (e.g., CORQUENCH). On this basis, an analysis has been carried out to further evaluate ex-vessel behavior for 1F1 using MELTSPREAD and CORQUENCH. Best-estimate melt pour conditions predicted by MELCOR v2.1 and MAAP5 were used as input. MELTSPREAD was then used to predict the spatially-dependent melt conditions and extent of spreading during relocation from the vessel. Lastly, this information was then used as input for the long-term debris coolability analysis with CORQUENCH that is reported in a companion paper.
- Authors:
-
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Publication Date:
- Research Org.:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy
- OSTI Identifier:
- 1350684
- Grant/Contract Number:
- AC02-06CH11357
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Nuclear Technology
- Additional Journal Information:
- Journal Volume: 196; Journal Issue: 3; Journal ID: ISSN 0029-5450
- Publisher:
- American Nuclear Society (ANS)
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; Fukushima; ex-vessel; severe accident; spreading
Citation Formats
Farmer, M. T., Robb, K. R., and Francis, M. W. Fukushima Daiichi Unit 1 ex-vessel prediction: Core melt spreading. United States: N. p., 2016.
Web. doi:10.13182/NT16-44.
Farmer, M. T., Robb, K. R., & Francis, M. W. Fukushima Daiichi Unit 1 ex-vessel prediction: Core melt spreading. United States. https://doi.org/10.13182/NT16-44
Farmer, M. T., Robb, K. R., and Francis, M. W. Mon .
"Fukushima Daiichi Unit 1 ex-vessel prediction: Core melt spreading". United States. https://doi.org/10.13182/NT16-44. https://www.osti.gov/servlets/purl/1350684.
@article{osti_1350684,
title = {Fukushima Daiichi Unit 1 ex-vessel prediction: Core melt spreading},
author = {Farmer, M. T. and Robb, K. R. and Francis, M. W.},
abstractNote = {Lower head failure and corium-concrete interaction were predicted to occur at Fukushima Daiichi Unit 1 (1F1) by several different system-level code analyses, including MELCOR v2.1 and MAAP5. Although these codes capture a wide range of accident phenomena, they do not contain detailed models for ex-vessel core melt behavior. However, specialized codes exist for analysis of ex-vessel melt spreading (e.g., MELTSPREAD) and long-term debris coolability (e.g., CORQUENCH). On this basis, an analysis has been carried out to further evaluate ex-vessel behavior for 1F1 using MELTSPREAD and CORQUENCH. Best-estimate melt pour conditions predicted by MELCOR v2.1 and MAAP5 were used as input. MELTSPREAD was then used to predict the spatially-dependent melt conditions and extent of spreading during relocation from the vessel. Lastly, this information was then used as input for the long-term debris coolability analysis with CORQUENCH that is reported in a companion paper.},
doi = {10.13182/NT16-44},
journal = {Nuclear Technology},
number = 3,
volume = 196,
place = {United States},
year = {Mon Oct 31 00:00:00 EDT 2016},
month = {Mon Oct 31 00:00:00 EDT 2016}
}
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