Fukushima Daiichi Unit 1 Ex-Vessel Prediction: Core-Concrete Interaction
نویسندگان
چکیده
منابع مشابه
Fukushima Daiichi Unit 1 Accident Progression Uncertainty Analysis and Implications for Decommissioning of Fukushima Reactors ? Volume I
Sandia National Laboratories (SNL) has conducted an uncertainty analysis (UA) on the Fukushima Daiichi unit (1F1) accident progression with the MELCOR code. The model used was developed for a previous accident reconstruction investigation jointly sponsored by the US Department of Energy (DOE) and Nuclear Regulatory Commission (NRC). That study focused on reconstructing the accident progressions...
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ژورنال
عنوان ژورنال: Nuclear Technology
سال: 2016
ISSN: 0029-5450,1943-7471
DOI: 10.13182/nt16-48