@inproceedings{663f06736fb442779c0754adea449e80,
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 IF 1 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. This information was then used as input for the long-term debris coolability analysis with CORQUENCH that is reported in a companion paper.",
keywords = "Ex-vessel, Fukushima, Severe accident, Spreading",
author = "Farmer, {M. T.} and Robb, {K. R.} and Francis, {M. W.}",
year = "2015",
language = "English",
series = "International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015",
publisher = "American Nuclear Society",
pages = "7537--7551",
booktitle = "International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015",
note = "16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 ; Conference date: 30-08-2015 Through 04-09-2015",
}