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dc.contributor.authorTohver, Hando
dc.contributor.authorMotlep, Riho
dc.contributor.authorKrasnikovs, Andrejs
dc.contributor.authorNovakova, Iveta
dc.contributor.authorGulik, Volodymyr
dc.contributor.authorSlavickas, Andrius
dc.contributor.authorHoliuk, Maryna
dc.contributor.authorVaišnoras, Mindaugas
dc.date.accessioned2024-01-17T12:46:10Z
dc.date.available2024-01-17T12:46:10Z
dc.date.issued2023-12-12
dc.description.abstractCement-based concretes are commonly used for managing radioactive waste due to their low cost and radiation shielding properties. However, the potential of using oil shale ash as an additive in waste packaging material has been overlooked. This study focuses on benchmarking and developing a Monte Carlo based modeling methodology using multiple transport codes (MCNP, SERPENT, SCALE, OpenMC, and EGSnrc) to assess the effects of these additives on the gamma and neutron shielding properties of concrete. The cross-code comparison showed that all transport codes are in excellent agreement with each other. Investigations into oil shale ash demonstrated similar properties to fly ash. The addition of oil shale ash had a negligible effect on low-level waste (LLW) gamma shielding properties and a minor negative effect on neutron shielding properties. The addition of basalt-boron fibers indicated a minor negative effect on LLW gamma shielding properties but a significant positive effect on neutron shielding properties. The presence of basalt-boron fibers considerably decreased the photon flux resulting from the activation of concrete. In conclusion, this study offers valuable insights into utilizing radiation transport codes to analyze the interactions between radiation particles and innovative concrete additives.en_US
dc.identifier.citationTohver, Motlep, Krasnikovs, Novakova, Gulik. Assessing shielding material Performance: Benchmarking of Monte Carlo codes for oil shale and Basalt-Boron fiber concretes Hando Tohver a,* , Andrius Slavickas b , Maryna Holiuk c , Andrejs Krasn¸ i. Nuclear Engineering and Design. 2023en_US
dc.identifier.cristinIDFRIDAID 2213242
dc.identifier.doi10.1016/j.nucengdes.2023.112811
dc.identifier.issn0029-5493
dc.identifier.issn1872-759X
dc.identifier.urihttps://hdl.handle.net/10037/32531
dc.language.isoengen_US
dc.publisherElsevieren_US
dc.relation.journalNuclear Engineering and Design
dc.rights.accessRightsopenAccessen_US
dc.rights.holderCopyright 2023 The Author(s)en_US
dc.rights.urihttps://creativecommons.org/licenses/by-nc/4.0en_US
dc.rightsAttribution-NonCommercial 4.0 International (CC BY-NC 4.0)en_US
dc.titleAssessing shielding material Performance: Benchmarking of Monte Carlo codes for oil shale and Basalt-Boron fiber concretes Hando Tohver a,* , Andrius Slavickas b , Maryna Holiuk c , Andrejs Krasn¸ ien_US
dc.type.versionpublishedVersionen_US
dc.typeJournal articleen_US
dc.typeTidsskriftartikkelen_US
dc.typePeer revieweden_US


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Attribution-NonCommercial 4.0 International (CC BY-NC 4.0)
Med mindre det står noe annet, er denne innførselens lisens beskrevet som Attribution-NonCommercial 4.0 International (CC BY-NC 4.0)