Abstract
The Monte Carlo method has high potential to provide very accurate solutions for particle transport problems appeared in nuclear engineering field because it can directly treat complex geometry, accurate physics models and fine structure nuclear data. New Monte Carlo codes have been developed for general purpose use on vector supercomputers and parallel computer environments. The quality of Monte Carlo codes depends significantly on their computation speed. Our codes realize a speedup factor of X15 compared with conventional scalar codes. Validation of codes was carried out by solving various benchmark problems and analyzing experiments.
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© 1997 IFIP International Federation for Information Processing
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Nakagawa, M. (1997). Development of efficient general purpose Monte Carlo codes used in nuclear engineering. In: Boisvert, R.F. (eds) Quality of Numerical Software. IFIP Advances in Information and Communication Technology. Springer, Boston, MA. https://doi.org/10.1007/978-1-5041-2940-4_31
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DOI: https://doi.org/10.1007/978-1-5041-2940-4_31
Publisher Name: Springer, Boston, MA
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