Skip to main content
×
×
Home

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

  • A. A. P. Macedo (a1), Carlos E. Velasquez (a1), C. A. M. da Silva (a1) (a2) and C. Pereira (a1) (a2)
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 ( k inf ) 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.

Copyright
Corresponding author
*E-mail: claubia@nuclear.ufmg.br
References
Hide All
1. Reyes-Ramírez, R., Martín-del-Campo, C., François, J., Brun, E., Dumonteil, E., Malvagi, F.. Comparison of MCNPX-C90 and TRIPOLI-4-D for fuel depletion calculations of a Gas-cooled Fast Reactor. Annals of Nuclear Energy 37, 11011106, (2010).
2. Martín-del-Campo, C., Reyes-Ramírez, R., François, J., Reinking-Cejudo, A. G.. Contributions to the neutronic analysis of a gas-cooled fast reactor. Annals of Nuclear Energy 38, 1406–141,(2011).
3. Martín-del-Campo, C., Reyes-Ramírez, R., François, J.. Validation of simplified methods for fuel depletion calculations in gas-cooled fast reactors. Annals of Nuclear Energy 60, 218225, (2013).
4. Ječmenica, R., Matijević, M., Pevec, D., Trontl, K.. Fuel Depletion Modeling of a Gas-cooled Fast Reactor Using the SCALE6.0 Code Package. 20 th International Conference Nuclear Energy for New Europe, (2011).
5. Goluoglu, S., Hollenbach, D. F., Petrie, L. M.. CSAS6: Control Module For Enchanced Criticality Safety Analisys With KENO-VI”. OAK Ridge National Laboratory, U.S. Department of Energy, ORNL/TM-2005/39 Version 6 Vol. I, Sect. C6 (2009).
6. Hollenbach, D. F., Petrie, L. M., Goluoglu, S., Landers, N. F., Dunn, M. E.. KENO-VI: A General Quadratic Program Version of the KENO Program. OAK Ridge National Laboratory, U.S. Department of Energy, ORNL/TM-2005/39 Version 6 Vol. II, Sect. F17, (2009).
7. DeHart, M. D.. TRITON: A two-Dimentional Transport and Depletion Module for Characterization of Spent Nuclear. OAK Ridge National Laboratory, U.S. Department of Energy, ORNL/TM-2005/39 Version 6 Vol. I, Sect. T1, (2009).
8. Bowman, S. M., Dunn, M. E.. SCALE Coss-Section Libraries. OAK Ridge National Laboratory, U.S. Department of Energy ORNL/TM-2005/39 Version 6 Vol. III, Sect. M4, (2009).
9. Generation IV International Forum, “2008 Annual Report”, (2008).
10. GEN-IV International Forum Paris, France 9-10 September, (2009).
Recommend this journal

Email your librarian or administrator to recommend adding this journal to your organisation's collection.

MRS Online Proceedings Library (OPL)
  • ISSN: -
  • EISSN: 1946-4274
  • URL: /core/journals/mrs-online-proceedings-library-archive
Please enter your name
Please enter a valid email address
Who would you like to send this to? *
×

Keywords

Metrics

Full text views

Total number of HTML views: 0
Total number of PDF views: 0 *
Loading metrics...

Abstract views

Total abstract views: 0 *
Loading metrics...

* Views captured on Cambridge Core between <date>. This data will be updated every 24 hours.

Usage data cannot currently be displayed