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dc.contributor.authorFletcher, Jack W
dc.contributor.authorPeterson, Ethan E
dc.contributor.authorTrelewicz, Jason R
dc.contributor.authorSnead, Lance L
dc.date.accessioned2025-10-22T17:39:13Z
dc.date.available2025-10-22T17:39:13Z
dc.date.issued2025-08-04
dc.identifier.urihttps://hdl.handle.net/1721.1/163370
dc.description.abstractWe present the process and results of neutronics-driven shielding design using metal and ceramic matrix metal hydride neutron shields within the context of compact, high-power tokamaks. In particular, hafnium hydrides were considered within a matrix of stainless steel or magnesium oxide and contrasted with established and novel fast neutron shielding materials. These shielding materials are found to substantially increase the lifetime of toroidal field magnets made of high-temperature superconductors by a factor of up to 14.5. Specifically, a stainless steel–20% HfH1.7 thermal shield and outer neutron shield, paired with an inner tungsten carbide (WC) shield and toroidal field magnet case and winding pack both doped with 40% HfH1.7 by volume, were found to achieve a 93.1% reduction in peak fast neutron flux to high-temperature superconductor tapes. Simultaneously, this configuration reduced the total mass (and cost) of the neutron shield, as well as the nuclear heating rate of the magnet coil, in comparison to monolithic shields of WC and boron carbide.en_US
dc.language.isoen
dc.publisherTaylor & Francisen_US
dc.relation.isversionofhttps://doi.org/10.1080/15361055.2025.2514910en_US
dc.rightsCreative Commons Attributionen_US
dc.rights.urihttps://creativecommons.org/licenses/by/4.0/en_US
dc.sourceTaylor & Francisen_US
dc.titleDesign and Performance of Metal Hydride Composite Neutron Shields for Compact, High-Power Fusion Reactorsen_US
dc.typeArticleen_US
dc.identifier.citationFletcher, J. W., Peterson, E. E., Trelewicz, J. R., & Snead, L. L. (2025). Design and Performance of Metal Hydride Composite Neutron Shields for Compact, High-Power Fusion Reactors. Fusion Science and Technology, 1–16.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Plasma Science and Fusion Centeren_US
dc.relation.journalFusion Science and Technologyen_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.updated2025-10-22T17:27:26Z
dspace.orderedauthorsFletcher, JW; Peterson, EE; Trelewicz, JR; Snead, LLen_US
dspace.date.submission2025-10-22T17:27:31Z
mit.licensePUBLISHER_CC


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