Parallel iterative algorithms for solving fundamental mode neutron flux distribution

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Date

1991

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Elsevier

Abstract

Issues relating to implementing iterative procedures, for numerical solution of neutron diffusion equations on a distributed parallel computing system, are discussed. Preliminary investigations for a reactor modelled on a 128 × 128 rectangular grid show that a speed-up of about 3.85 is achievable on a fourtransputer pipeline network.

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Keywords

Management, Neutron flux

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