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Effects on Criticality and Burnup Calculations Changings ADS Cladding Material

Published online by Cambridge University Press:  07 March 2016

Carlos E. Velasquez
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais Avenida Antônio Carlos, 6627, Pampulha 31270-901 – Belo Horizonte, Tel/Fax: 55-31-34096662, MG, Brasil Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/CNPq, Brazil
G. Barros
Affiliation:
CNEN - Comissão Nacional de Energia Nuclear Rua Gal Severiano, n° 90 - Botafogo; 22290-901, Rio de Janeiro - RJ - Brasil
M. A. F. Veloso
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais Avenida Antônio Carlos, 6627, Pampulha 31270-901 – Belo Horizonte, Tel/Fax: 55-31-34096662, MG, Brasil Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/CNPq, Brazil
A. L. Costa
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais Avenida Antônio Carlos, 6627, Pampulha 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 Avenida Antônio Carlos, 6627, Pampulha 31270-901 – Belo Horizonte, Tel/Fax: 55-31-34096662, MG, Brasil Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/CNPq, Brazil
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Abstract

One of the most important parts of a hybrid reactor is the cladding because it should withstand high temperatures, neutrons with high energy, high neutron flux, as well as provide the first security contention. Besides, the material should have good mechanical properties to remove the heat. Although, the cladding material choice will have a great influence on criticality calculations. In previous works on ADS there is no cladding used, therefore in this paper it is tested different cladding materials based on SS-316, ODS, T91 and 15-15Ti used in nuclear reactors, to study the variations on the fuel depletion and variations on the neutronic parameters. The results using the cladding are compared with the one obtained without using it. The best material choice is based on the neutronic parameters that presents the closest behavior to the ADS simulated without clad.

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Copyright
Copyright © Materials Research Society 2016 

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