Implementation and qualification of neutronic calculation methodology in subcritical reactors driven by external neutron sources and applications / Implementação  e qualificação de metodologia de cálculos neutrônicos em reatores subcríticos acionados por fontes externa de nêutrons e aplicações

AUTOR(ES)
FONTE

IBICT - Instituto Brasileiro de Informação em Ciência e Tecnologia

DATA DE PUBLICAÇÃO

19/08/2011

RESUMO

This works had as goal to investigate calculational methodologies on subcritical source driven reactor, such as Accelerator Driven Subcritical Reactor (ADSR) and Fusion Driven Subcritical Reactor (FDSR). Intense R&D has been done about these subcritical concepts, mainly due to Minor Actinides(MA) and Long Lived Fission Products(LLFP) transmutation possibilities. In this work, particular emphasis has been given to: (i ) complement and improve calculation methodology with neutronic transmutation and decay capabilities and implement it computationally, (ii ) utilization of this methodology in the Coordinated Research Project (CRP) of the International Atomic Energy Agency Analytical and Experimental Benchmark Analysis of ADS and in the Collaborative Work on Use of Low Enriched Uranium in ADS, especially in the reproduction of the experimental results of the Yalina Booster subcritical assembly and study of a subcritical core of IPEN/MB-01 reactor, (iii ) to compare dierent nuclear data libraries calculation of integral parameters,such as keff and ksrc, and dierential distributions, such as spectrum and ux, and nuclides inventories and (iv ) apply the developed methodology in a study that may help future choices about dedicated transmutation system. The following tools have been used in this work: MCNP (Monte Carlo N particle transport code), MCB (enhanced version of MCNP that allows burnup calculation) and NJOY to process nuclear data from evaluated nuclear data files.

ASSUNTO(S)

fusão ads ads cálculos neutrônicos fusion hybrid neutronic calculation reatores híbridos transmutação transmutation

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