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dc.creatorPešić, Milan P.
dc.creatorNinković, Marko M.
dc.date.accessioned2018-03-01T18:44:03Z
dc.date.available2018-03-01T18:44:03Z
dc.date.issued1999
dc.identifier.issn0017-9078 (print)
dc.identifier.issn1538-5159 (electronic)
dc.identifier.urihttp://vinar.vin.bg.ac.rs/handle/123456789/2266
dc.description.abstractThe RE experimental reactor has operated at Vinca Institute of Nuclear Sciences since the end of April 1958. Tn this paper, neutron and gamma-ray spectra and corresponding dose quantities near the reactor, calculated by using the MCNP(TM) code, are compared to the measured values during the Third International Intercomparison Experiment on Nuclear Accident Dosimetry carried out at the RE reactor in 1973. Discrepancies in the correlation declared power of the reactor-dose rates are found. Good agreements are obtained between measured and calculated neutron and gamma-ray spectra, and corresponding absorbed doses in air, but only after the reactor declared power is multiplied by a correction factor, determined in this study.en
dc.rightsrestrictedAccessen
dc.sourceHealth Physicsen
dc.subjectMonte Carloen
dc.subjectnuclear accidentsen
dc.subjectdose, absorbeden
dc.subjectgamma radiationen
dc.titleComparison of the MCNP (TM) calculated and measured radiation field quantities near the RB reactoren
dc.typearticleen
dcterms.abstractПесиц, МП; Нинковиц, ММ;
dc.citation.volume77
dc.citation.issue3
dc.citation.spage276
dc.citation.epage281
dc.identifier.wos000082009800005
dc.identifier.doi10.1097/00004032-199909000-00005
dc.citation.rankM22
dc.identifier.pmid10456498


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