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handle: 11380/618100
The present work describes an improved version of the computer code BACCHUS-T to analyse the thermohydraulic features of the coolant flow in the fuel bundle of a LMFBR.The improvement mainly consists in the development of a numerical algorithm, based on the finite element method, in order to predict the temperature distribution in the fuel, gap and cladding regions, in transient conditions. Also mechanical and thermoelastic stresses can be determined.
nuclear plants; numerical simulations
nuclear plants; numerical simulations
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