Table of Contents
International Journal of Nuclear Energy
Volume 2014, Article ID 279073, 12 pages
Research Article

Computational Model for the Neutronic Simulation of Pebble Bed Reactor’s Core Using MCNPX

1Higher Institute of Technologies and Applied Sciences (InSTEC), Avenida Salvador Allende Esq. Luaces, Quinta de los Molinos, 10600 Havana, Cuba
2European Organization for Nuclear Research, Route de Meyrin 385, 1217 Meyrin, Switzerland
3Department of Nuclear Energy, Federal University of Pernambuco, Avenida Prof. Luiz Freire, 1000 Cidade Universitária, 50740540 Recife, PE, Brazil
4School of Industrial Engineering, C/ José Gutiérrez Abascal, No. 2, 28006 Madrid, Spain

Received 2 June 2014; Accepted 12 August 2014; Published 17 September 2014

Academic Editor: Shuisheng He

Copyright © 2014 J. Rosales et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.


Very high temperature reactor (VHTR) designs offer promising performance characteristics; they can provide sustainable energy, improved proliferation resistance, inherent safety, and high temperature heat supply. These designs also promise operation to high burnup and large margins to fuel failure with excellent fission product retention via the TRISO fuel design. The pebble bed reactor (PBR) is a design of gas cooled high temperature reactor, candidate for Generation IV of Nuclear Energy Systems. This paper describes the features of a detailed geometric computational model for PBR whole core analysis using the MCNPX code. The validation of the model was carried out using the HTR-10 benchmark. Results were compared with experimental data and calculations of other authors. In addition, sensitivity analysis of several parameters that could have influenced the results and the accuracy of model was made.