This paper explores the capability of the MELCOR 2.2 code, initially developed for the simulation of LWR severe accidents, to model the thermal evolution of SNF concrete dry casks. Given the outstanding differences between a severe accident and a dry cask storage, a good number of approximations and hypotheses have been made so that the models available in MELCOR are employed in the best consistent way possible.
Thermal characterization with the MELCOR code of the nuclear fuel stored in dry concrete casks
M. Angelucci;S. PaciUltimo
2019-01-01
Abstract
This paper explores the capability of the MELCOR 2.2 code, initially developed for the simulation of LWR severe accidents, to model the thermal evolution of SNF concrete dry casks. Given the outstanding differences between a severe accident and a dry cask storage, a good number of approximations and hypotheses have been made so that the models available in MELCOR are employed in the best consistent way possible.File in questo prodotto:
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