GPU-based Monte Carlo simulation in neutron transport and finite differences heat equation evaluation
Laboratorio de Inteligencia Artificial Aplicada, Comissao Nacional de Energia Nuclear, IEN/CNEN, R. Helio de Almeida, 75, 21941-972 Ilha do Fundao, P.O. Box 68550, Rio de Janeiro, Brazil
Progress in Nuclear Energy (03 December 2010)
@article{heimlichgpubased,
title={GPU-based Monte Carlo simulation in neutron transport and finite differences heat equation evaluation},
author={Heimlich, A. and Mol, A.C.A. and Pereira, C.M.N.A.},
journal={Progress in Nuclear Energy},
publisher={Elsevier Ltd.}
}
Graphics Processing Units (GPU) are high performance co-processors originally intended to improve the use and quality of computer graphics applications. Since researchers and practitioners realized the potential of using GPU for general purpose, their application has been extended to other fields out of computer graphics scope. The main objective of this work is to evaluate the impact of using GPU in two computational expensive problems in nuclear area: a neutron transport simulation by Monte Carlo method and Poison heat equation resolution for a square thin plate. To accomplish that, GPU and CPU-based (single- and multi-core) approaches were developed. Results demonstrated that the GPU-based approach is damn faster than a parallel 8-core CPU-based approach also developed in this work.
December 7, 2010 by hgpu
