A Comprehensive Approach to Molten Salt Reactor Source Term Generation and Shielding Analyses

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dc.contributor.authorCarberry, Kyle
dc.contributor.authorPetrovic, Bojan
dc.date.accessioned2024-04-08T15:11:38Z
dc.date.available2024-04-08T15:11:38Z
dc.date.issued2023-07-24
dc.description.abstractThe research presented herein outlines a comprehensive process for characterizing the major radiological source terms necessary for radiation protection and licensing activities that one would expect in a liquid-fueled molten salt reactor. This process leverages organic simulation tools in the SCALE modeling and simulation code suite to provide an “off-the-shelf” solution for shielding assessments of this reactor type. Ultimately, this source development process is applied to a representative molten salt reactor system to assess the impact of ex-core source terms on shielding in varying operating conditions. The results of the analysis determined that while the prompt core source is the major dose contributor outside the radiological shielding, specific ex-core features, such as the primary salt loop components and configuration, can have an appreciable dose impact, and thus must be accounted for.
dc.description.sponsorshipThis work was supported, in part, by the Nuclear Energy eXperimental Testing Research Alliance (NEXTRA) with funding provided by Natura Resources, LLC, as well as through research cyberinfrastructure resources and services provided by the Partnership for an Advanced Computing Environment (PACE) at the Georgia Institute of Technology, Atlanta, Georgia, USA.
dc.identifier.citationCarberry, Kyle, and Bojan Petrovic. “A Comprehensive Approach to Molten Salt Reactor Source Term Generation and Shielding Analyses.” Nuclear Technology 210, no. 3 (2024): 409–35. doi:10.1080/00295450.2023.2229181.
dc.identifier.doihttps://doi.org/10.1080/00295450.2023.2229181
dc.identifier.issn0029-5450
dc.identifier.issn1943-7471
dc.identifier.urihttps://hdl.handle.net/20.500.14216/1473
dc.publisherInforma UK Limited
dc.relation.ispartofNuclear Technology
dc.relation.ispartofseries210; 3
dc.subjectMolten Salt reactor source terms
dc.subjectSCALE
dc.subjectvariance reduction
dc.subjectprompt and delayed neutrons
dc.subjectneutron and gamma dose rate
dc.titleA Comprehensive Approach to Molten Salt Reactor Source Term Generation and Shielding Analyses
dc.typeJournal articles
local.USMAemailkyle.carberry@westpoint.edu
local.peerReviewedYes
oaire.citation.issue3
oaire.citation.volume210

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