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MELCOR Simulations of the Severe Accident at the Fukushima Daiichi Unit 1 Reactor

Authors :
Jeffrey N Cardoni
Donald A. Kalinich
Randall O. Gauntt
Jesse Phillips
Source :
Nuclear Technology. 186:161-178
Publication Year :
2014
Publisher :
Informa UK Limited, 2014.

Abstract

In response to the accident at the Fukushima Daiichi nuclear power station in Japan, the U.S. Nuclear Regulatory Commission and U.S. Department of Energy agreed to jointly sponsor an accident reconstruction study as a means of assessing the severe accident modeling capability of the MELCOR code and developing an understanding of the likely accident progression. Objectives of the project included reconstruction of the accident progressions using computer models and accident data, and validation of MELCOR and the Fukushima models against plant data. In this study Sandia National Laboratories developed MELCOR 2.1 models of Fukushima Daiichi Units 1 (1F1), 2, and 3 as well as the Unit 4 spent fuel pool. This paper reports on the analysis of the 1F1 accident. Details are presented on the modeled accident progression, hypothesized mode of failures in the reactor pressure vessel (RPV) and containment pressure boundary, and release of fission products to the environment. The MELCOR-predicted RPV and conta...

Details

ISSN :
19437471 and 00295450
Volume :
186
Database :
OpenAIRE
Journal :
Nuclear Technology
Accession number :
edsair.doi...........eeae038429a4d26458fd4f6ddac4116f
Full Text :
https://doi.org/10.13182/nt13-59