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Assessment of the Insertion of Reprocessed Fuels and Combined Thorium Fuel Cycles in a PWR System

Published online by Cambridge University Press:  13 February 2015

Fabiana. B. A. Monteiro ,
Rochkhudson. B. de Faria ,
Ângela Fortini ,
Clarysson A. M. Da Silva  and
Cláubia Pereira
Fabiana. B. A. Monteiro
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
Rochkhudson. B. de Faria
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
Ângela Fortini
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
Clarysson A. M. Da Silva
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
Cláubia 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
*
*[email protected]
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Abstract

The insertion of reprocessed fuel spiked with thorium in a typical PWR fuel element considering (TRU-Th) cycle was simulated using different fissile materials that varied from 5.5% 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 kinf, hardening spectrum and the fuel evolution during the burnup were evaluated. This study was performed using the SCALE 6.0

Keywords

advanced fuelthoriumPWR
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1769: Symposium 6E – Materials for Nuclear Applications , 2015 , IMRC 2014 6E-13
Copyright
Copyright © Materials Research Society 2015 

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References

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