An easy to implement global variance reduction procedure for MCNP

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In this article, an easy to implement global variance reduction procedure is demonstrated. The procedure is capable of flattening the relative error distribution in a global mesh tally covering the geometry of a complex system. The method is fully based on the I/O capabilities of the MCNP Monte Carlo radiation transport code family and requires little additional support code and almost no user judgment to work properly. Increases, with respect to a standard simulation, in a global figure of merit ranging up to a factor 276 for a PWR core configuration have been observed. Also, the relative error distribution was flattened substantially in all studied systems by the application of the procedure and the number of empty mesh tally cells was reduced.


Original languageEnglish
Pages (from-to)2496-2503
JournalAnnals of nuclear energy
Issue number11
Publication statusPublished - Nov 2011


  • Variance reduction, MCNP

ID: 134236