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NEUTRONIC PERFORMANCE OF (U, Pu)C FUEL IN A LATTICE OF GFR USING SCALE 6.0

Published online by Cambridge University Press:  08 March 2016

A. A. P. Macedo ,
Carlos E. Velasquez ,
C. A. M. da Silva  and
C. Pereira
A. A. P. Macedo*
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais, Av. Antônio Carlos, 6627, Pampulha, CEP 31270-901 Belo Horizonte, Tel/Fax: 55-31-34096662, MG, Brasil
Carlos E. Velasquez
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais, Av. Antônio Carlos, 6627, Pampulha, CEP 31270-901 Belo Horizonte, Tel/Fax: 55-31-34096662, MG, Brasil
C. A. M. da Silva
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais, Av. Antônio Carlos, 6627, Pampulha, CEP 31270-901 Belo Horizonte, Tel/Fax: 55-31-34096662, MG, Brasil Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/CNPq, Brazil
C. Pereira
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais, Av. Antônio Carlos, 6627, Pampulha, CEP 31270-901 Belo Horizonte, Tel/Fax: 55-31-34096662, MG, Brasil Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/CNPq, Brazil
*
*E-mail: [email protected]
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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.

Keywords

Neutron irradiationNuclear materialWaste management
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1814: Symposium 6H – Materials in Nuclear Science and Technology—2015 , 2016 , imrc2015sim28-abs016
Copyright
Copyright © Materials Research Society 2016 

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References

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