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Title: 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:
 [1];  [2];  [2]
  1. Argonne National Lab. (ANL), Argonne, IL (United States)
  2. 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:
Journal Article: 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. doi: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. doi: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},
issn = {0029-5450},
number = 3,
volume = 196,
place = {United States},
year = {2016},
month = {10}
}

Journal Article:
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Cited by: 1 work
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