Table of Contents
International Journal of Nuclear Energy
Volume 2014, Article ID 793934, 9 pages
http://dx.doi.org/10.1155/2014/793934
Research Article

Sensitivity Analysis of the TRIGA IPR-R1 Reactor Models Using the MCNP Code

1Departamento de Engenharia Nuclear, Escola de Engenharia, Universidade Federal de Minas Gerais, Campus Pampulha, Avenida Presidente Antônio Carlos 6627, 31270-901 Belo Horizonte, MG, Brazil
2Centro de Desenvolvimento da Tecnologia Nuclear, Comissão Nacional de Energia Nuclear, Campus Pampulha, Avenida Presidente Antônio Carlos 6627, P.O. Box 941, 31270-901, Belo Horizonte, MG, Brazil

Received 11 April 2014; Accepted 23 July 2014; Published 9 September 2014

Academic Editor: Arkady Serikov

Copyright © 2014 C. A. M. Silva 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.

Abstract

In the process of verification and validation of code modelling, the sensitivity analysis including systematic variations in code input variables must be used to help identifying the relevant parameters necessary for a determined type of analysis. The aim of this work is to identify how much the code results are affected by two different types of the TRIGA IPR-R1 reactor modelling processes performed using the MCNP (Monte Carlo N-Particle Transport) code. The sensitivity analyses included small differences of the core and the rods dimensions and different levels of model detailing. Four models were simulated and neutronic parameters such as effective multiplication factor (), reactivity (), and thermal and total neutron flux in central thimble in some different conditions of the reactor operation were analysed. The simulated models presented good agreement between them, as well as in comparison with available experimental data. In this way, the sensitivity analyses demonstrated that simulations of the TRIGA IPR-R1 reactor can be performed using any one of the four investigated MCNP models to obtain the referenced neutronic parameters.