Numerical analysis of an incremented statistical sampling procedure in MCNP

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dc.contributor.authorSIQUEIRA, PAULO de T.D.pt_BR
dc.contributor.authorYORIYAZ, HELIOpt_BR
dc.contributor.authorSANTOS, ADIMIR dospt_BR
dc.contributor.authorPASCHOLATI, PAULO R.pt_BR
dc.coverageInternacionalpt_BR
dc.date.accessioned2014-07-15T13:43:10Zpt_BR
dc.date.accessioned2014-07-30T11:51:22Z
dc.date.available2014-07-15T13:43:10Zpt_BR
dc.date.available2014-07-30T11:51:22Z
dc.date.issued2008pt_BR
dc.description.abstractMCNP has stood so far as one of the main Monte Carlo radiation transport codes. Its use, as any other Monte Carlo based code, has increased as computers perform calculations faster and become more affordable along time. However, the use of Monte Carlo method to tally events in volumes which represent a small fraction of the whole system may turn to be unfeasible, if a straight analogue transport procedure (no use of variance reduction techniques) is employed and precise results are demanded. Calculations of reaction rates in activation foils placed in critical systems turn to be one of the mentioned cases. The present work takes advantage of the fixed source representation from MCNP to perform the above mentioned task in a more effective sampling way (characterizing neutron population in the vicinity of the tallying region and using it in a geometric reduced coupled simulation). An extended analysis of source dependent parameters is studied in order to understand their influence on simulation performance and on validity of results. Although discrepant results have been observed for small enveloping regions, the procedure presents itself as very efficient, giving adequate and precise results in shorter times than the standard analogue procedure.
dc.format.extent1073-1086pt_BR
dc.identifier.citationSIQUEIRA, PAULO de T.D.; YORIYAZ, HELIO; SANTOS, ADIMIR dos; PASCHOLATI, PAULO R. Numerical analysis of an incremented statistical sampling procedure in MCNP. <b>Annals of Nuclear Energy</b>, v. 35, p. 1073-1086, 2008. DOI: <a href="https://dx.doi.org/10.1016/j.anucene.2007.11.004">10.1016/j.anucene.2007.11.004</a>. Disponível em: http://repositorio.ipen.br/handle/123456789/5003.
dc.identifier.doi10.1016/j.anucene.2007.11.004
dc.identifier.issn0306-4549pt_BR
dc.identifier.orcidhttps://orcid.org/0000-0002-5989-5705
dc.identifier.orcidhttps://orcid.org/0000-0003-4023-236X
dc.identifier.urihttp://repositorio.ipen.br/handle/123456789/5003pt_BR
dc.identifier.vol35pt_BR
dc.relation.ispartofAnnals of Nuclear Energypt_BR
dc.rightsopenAccessen
dc.subjectmonte carlo methodpt_BR
dc.subjectm codespt_BR
dc.subjectsimulationpt_BR
dc.subjectradiation transportpt_BR
dc.subjectanalog systemspt_BR
dc.titleNumerical analysis of an incremented statistical sampling procedure in MCNPpt_BR
dc.typeArtigo de periódicopt_BR
dspace.entity.typePublication
ipen.autorADIMIR DOS SANTOS
ipen.autorHELIO YORIYAZ
ipen.autorPAULO DE TARSO DALLEDONE SIQUEIRA
ipen.codigoautor35
ipen.codigoautor80
ipen.codigoautor968
ipen.contributor.ipenauthorADIMIR DOS SANTOS
ipen.contributor.ipenauthorHELIO YORIYAZ
ipen.contributor.ipenauthorPAULO DE TARSO DALLEDONE SIQUEIRA
ipen.date.recebimento09-04pt_BR
ipen.identifier.fi0.831pt_BR
ipen.identifier.ipendoc13680pt_BR
ipen.identifier.iwosWoSpt_BR
ipen.range.fi0.001 - 1.499
ipen.type.genreArtigo
relation.isAuthorOfPublication028075df-b2b9-4e6a-a300-e744b2a9d63f
relation.isAuthorOfPublication93102dac-f89d-4743-b6ea-5158708cbb92
relation.isAuthorOfPublication24db5afe-fc9a-4cc0-9be3-2c5035796315
relation.isAuthorOfPublication.latestForDiscovery24db5afe-fc9a-4cc0-9be3-2c5035796315
sigepi.autor.atividadeSIQUEIRA, PAULO de T.D.:968:420:Spt_BR
sigepi.autor.atividadeYORIYAZ, HELIO:80:420:Npt_BR
sigepi.autor.atividadeSANTOS, ADIMIR DOS:35:420:Npt_BR
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