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dc.contributor.authorElsaidi, Sameh K.
dc.contributor.authorMohamed, Mona H.
dc.contributor.authorHelal, Ahmed S.
dc.contributor.authorGalanek, Mitchell
dc.contributor.authorPham, Tony
dc.contributor.authorSuepaul, Shanelle
dc.contributor.authorSpace, Brian
dc.contributor.authorHopkinson, David
dc.contributor.authorThallapally, Praveen K.
dc.contributor.authorLi, Ju
dc.date.accessioned2022-06-13T18:35:47Z
dc.date.available2021-10-27T19:51:39Z
dc.date.available2022-06-13T18:35:47Z
dc.date.issued2020-06
dc.date.submitted2019-10
dc.identifier.issn2041-1723
dc.identifier.urihttps://hdl.handle.net/1721.1/133232.2
dc.description.abstract© 2020, The Author(s). Capture and storage of volatile radionuclides that result from processing of used nuclear fuel is a major challenge. Solid adsorbents, in particular ultra-microporous metal-organic frameworks, could be effective in capturing these volatile radionuclides, including 85Kr. However, metal-organic frameworks are found to have higher affinity for xenon than for krypton, and have comparable affinity for Kr and N2. Also, the adsorbent needs to have high radiation stability. To address these challenges, here we evaluate a series of ultra-microporous metal-organic frameworks, SIFSIX-3-M (M = Zn, Cu, Ni, Co, or Fe) for their capability in 85Kr separation and storage using a two-bed breakthrough method. These materials were found to have higher Kr/N2 selectivity than current benchmark materials, which leads to a notable decrease in the nuclear waste volume. The materials were systematically studied for gamma and beta irradiation stability, and SIFSIX-3-Cu is found to be the most radiation resistant.en_US
dc.language.isoen
dc.publisherSpringer Science and Business Media LLCen_US
dc.relation.isversionofhttp://dx.doi.org/10.1038/s41467-020-16647-1en_US
dc.rightsCreative Commons Attribution 4.0 International licenseen_US
dc.rights.urihttps://creativecommons.org/licenses/by/4.0/en_US
dc.sourceNatureen_US
dc.titleRadiation-resistant metal-organic framework enables efficient separation of krypton fission gas from spent nuclear fuelen_US
dc.typeArticleen_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineering
dc.contributor.departmentMassachusetts Institute of Technology. Department of Materials Science and Engineering
dc.relation.journalNature Communicationsen_US
dc.eprint.versionFinal published versionen_US
dc.type.urihttp://purl.org/eprint/type/JournalArticleen_US
eprint.statushttp://purl.org/eprint/status/PeerRevieweden_US
dc.date.updated2021-08-12T14:46:40Z
dspace.orderedauthorsElsaidi, SK; Mohamed, MH; Helal, AS; Galanek, M; Pham, T; Suepaul, S; Space, B; Hopkinson, D; Thallapally, PK; Li, Jen_US
dspace.date.submission2021-08-12T14:46:42Z
mit.journal.volume11en_US
mit.journal.issue1en_US
mit.licensePUBLISHER_CC
mit.metadata.statusAuthority Work Neededen_US


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