Development of parallel GPU based algorithms for problems in nuclear area
Description
Graphics Processing Units (GPU) are high performance co-processors intended, originally, 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 typical problems of Nuclear area. The neutron transport simulation using Monte Carlo method and solve heat equation in a bi-dimensional domain by finite differences method. To achieve this, we develop parallel algorithms for GPU and CPU in the two problems described above. The comparison showed that the GPU-based approach is faster than the CPU in a computer with two quad core processors, without precision loss. (author)
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41033654.pdf
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Additional details
Additional titles
- Original title (Portuguese)
- Desenvolvimento de algoritmos paralelos baseados em GPU para solucao de problemas na area nuclear
Publishing Information
- Imprint Pagination
- 91 p.
- Report number
- INIS-BR--6548
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 41033654
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- ACCURACY; ALGORITHMS; COMPARATIVE EVALUATIONS; COMPUTER-GRAPHICS DEVICES; COMPUTERIZED SIMULATION; DATA PROCESSING; FINITE DIFFERENCE METHOD; FOURIER HEAT EQUATION; MONTE CARLO METHOD; NEUTRON TRANSPORT; TWO-DIMENSIONAL CALCULATIONS; USES
- Descriptors DEC
- CALCULATION METHODS; COMPUTER OUTPUT DEVICES; DIFFERENTIAL EQUATIONS; EQUATIONS; EVALUATION; ITERATIVE METHODS; MATHEMATICAL LOGIC; MATHEMATICAL SOLUTIONS; NEUTRAL-PARTICLE TRANSPORT; NUMERICAL SOLUTION; PARTIAL DIFFERENTIAL EQUATIONS; PROCESSING; RADIATION TRANSPORT; SIMULATION