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Micro Heteregeneous Approaches for the Insertion of Reprocessed and Combined Thorium Fuel Cycles in a PWR System

Published online by Cambridge University Press:  07 March 2016

Fabiana B. A. Monteiro ,
Victor F. Castro ,
Rochkhudson B. de Faria ,
Ângela Fortini ,
Clarysson A. M. Da Silva  and
Claubia Pereira
Fabiana B. A. Monteiro
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais Avenida Antônio Carlos, 6627, Pampulha Belo Horizonte, MG, Brasil Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/CNPq, Brazil
Victor F. Castro
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais Avenida Antônio Carlos, 6627, Pampulha Belo Horizonte, MG, Brasil
Rochkhudson B. de Faria
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais Avenida Antônio Carlos, 6627, Pampulha Belo Horizonte, MG, Brasil
Ângela Fortini
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais Avenida Antônio Carlos, 6627, Pampulha Belo Horizonte, MG, Brasil
Clarysson A. M. Da Silva
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais Avenida Antônio Carlos, 6627, Pampulha Belo Horizonte, MG, Brasil
Claubia Pereira
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais Avenida Antônio Carlos, 6627, Pampulha Belo Horizonte, MG, Brasil Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/CNPq, Brazil
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Abstract

A micro heteregenous reprocessed fuel spiked with thorium in a PWR fuel element considering (TRU-Th) cycle was simulated using three different configurations and different fissile materials that varied from 6.0% to 7.0%. The reprocessed fuels were obtained using the ORIGEN 2.1 code from a burned PWR standard fuel (33,000 MWd/tHM burned), with 3.1% of initial enrichment, which was remained in the cooling pool for five years and then reprocessed using UREX+ technique. The keff and plutonium generation during the burnup were evaluated and compared with the standard fuel. This study was performed using the SCALE 6.0.

Keywords

Nuclear materialsWaste managementSimulation
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1814: Symposium 6H – Materials in Nuclear Science and Technology—2015 , 2016 , imrc2015sim28-abs012
Copyright
Copyright © Materials Research Society 2016 

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References

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