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Neutron flux characterization of the beam port of the Missouri University of Science and Technology Reactor

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dc.contributor.authorAKYÜREK, TAYFUN
dc.contributor.authorsAlbarqi, Mubarak; Alsulami, Raed; Akyurek, Tayfun; Graham, Joseph
dc.date.accessioned2022-03-12T22:38:50Z
dc.date.accessioned2026-01-11T07:01:05Z
dc.date.available2022-03-12T22:38:50Z
dc.date.issued2019
dc.description.abstractNeutron activation analysis was used to determine the thermal and epithermal neutron flux and its spatial distribution at the beam port of the Missouri University of Science and Technology Research Reactor. Gold foil irradiations were conducted and the determined flux was compared to Monte Carlo radiation transport predictions using the Monte Carlo N-particle code. The average experimental thermal (E<0.55eV) and epithermal (0.55eV<E<100keV) fluxes were (5.7 +/- 0.3)x10(6)cm(-2)s(-1) and (7.3 +/- 0.3)x10(5)cm(-2)s(-1), respectively and were found to be in good qualitative agreement with the MCNP simulations.
dc.identifier.doi10.1007/s10967-019-06561-2
dc.identifier.eissn1588-2780
dc.identifier.issn0236-5731
dc.identifier.urihttps://hdl.handle.net/11424/235734
dc.identifier.wosWOS:000471967000010
dc.language.isoeng
dc.publisherSPRINGER
dc.relation.ispartofJOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY
dc.rightsinfo:eu-repo/semantics/closedAccess
dc.subjectFoil activation
dc.subjectNeutron activation analysis
dc.subjectNeutron flux characterization
dc.subjectMCNP
dc.subjectMonte Carlo
dc.subjectBeam port
dc.subjectSELF-SHIELDING FACTORS
dc.subjectCORE
dc.subjectPGAA
dc.titleNeutron flux characterization of the beam port of the Missouri University of Science and Technology Reactor
dc.typearticle
dspace.entity.typePublication
oaire.citation.endPage116
oaire.citation.issue1
oaire.citation.startPage109
oaire.citation.titleJOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY
oaire.citation.volume321

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