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Neutronic Performance of (U, PU)C Fuel in a Lattice of Gfr Using Scale 6.0

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Abstract

This paper studies the performance of (U, Pu)C fuel in a hexagonal assembly of a GFR (Gas Fast Reactor). The SCALE 6.0 (Standardized Computer Analysis for Licensing Evaluation version 6.0) code was used in the calculation. The goal is to evaluate the behavior of the infinite multiplication factor (kinf) for a heterogeneous assembly model using four nuclear data libraries: V6-238, V7-238, ENDF/B-VI.8 and ENDF/B-VII.0. The burnup of (U, Pu)C was performed by the TRITON-6 module, and the isotopic concentrations were evaluated during the cycle. The present work comprises calculations at Zero Power and Full Power condition. This study intends to achieve more information about different Fast Reactors.

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Authors and Affiliations

  1. Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais, Av. Antônio Carlos, 6627, Pampulha, CEP, 31270-901, Belo Horizonte, MG, Brasil

    A. A. P. Macedo, Carlos E. Velasquez, C. A. M. da Silva & C. Pereira

  2. Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/CNPq, Brazil

    C. A. M. da Silva & C. Pereira

Authors
  1. A. A. P. Macedo
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  2. Carlos E. Velasquez
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  3. C. A. M. da Silva
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  4. C. Pereira
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Correspondence to A. A. P. Macedo.

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Macedo, A.A.P., Velasquez, C.E., da Silva, C.A.M. et al. Neutronic Performance of (U, PU)C Fuel in a Lattice of Gfr Using Scale 6.0. MRS Online Proceedings Library 1814, 32 (2016). https://doi.org/10.1557/opl.2016.32

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  • DOI: https://doi.org/10.1557/opl.2016.32

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