Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core Melt Spreading

被引:3
作者
Farmer, M. T. [1 ]
Robb, K. R. [2 ]
Francis, M. W. [2 ]
机构
[1] Argonne Natl Lab, 9700 S Cass Ave, Argonne, IL 60439 USA
[2] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
关键词
Fukushima; ex-vessel; melt spreading;
D O I
10.13182/NT16-44
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
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 the 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. The 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 the extent of spreading during relocation from the vessel. This information was then used as input for the long-term debris coolability analysis with CORQUENCH, which is reported in a companion paper.
引用
收藏
页码:446 / 460
页数:15
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