A comprehensive Thermo-hydraulic neutronic and safety analysis of a 100MWth pebble bed reactor core

dc.contributor.authorBoyes, W.A.
dc.contributor.authorSlabber, Johan F.M.
dc.contributor.authorBoyes, D.W.
dc.date.accessioned2023-07-18T09:48:47Z
dc.date.issued2022-11
dc.descriptionDATA AVAILABILITY: Data will be made available on request.en_US
dc.description.abstractPlease read abstract in the article.en_US
dc.description.departmentMechanical and Aeronautical Engineeringen_US
dc.description.embargo2024-10-01
dc.description.librarianhj2023en_US
dc.description.librarianmi2025en
dc.description.sdgSDG-03: Good health and well-beingen
dc.description.sdgSDG-04: Quality educationen
dc.description.sdgSDG-07: Affordable and clean energyen
dc.description.sdgSDG-12: Responsible consumption and productionen
dc.description.sdgSDG-13: Climate actionen
dc.description.urihttps://www.elsevier.com/locate/nucengdesen_US
dc.identifier.citationBoyes, W.A., Slabber, J.F.M. & Boyes, D.W. 2022, 'A comprehensive Thermo-hydraulic neutronic and safety analysis of a 100MWth pebble bed reactor core', Nuclear Engineering and Design, vol. 398, art. 111991, pp. 1-12, doi : 10.1016/j.nucengdes.2022.111991.en_US
dc.identifier.issn0029-5493
dc.identifier.other10.1016/j.nucengdes.2022.111991
dc.identifier.urihttp://hdl.handle.net/2263/91506
dc.language.isoenen_US
dc.publisherElsevieren_US
dc.rights© 2022 Elsevier B.V. All rights reserved. Notice : this is the author’s version of a work that was accepted for publication in Nuclear Engineering and Design. Changes resulting from the publishing process, such as peer review, editing, corrections, structural formatting, and other quality control mechanisms may not be reflected in this document. A definitive version was subsequently published in Nuclear Engineering and Design, vol. 398, art. 111991, pp. 1-12, 2022, doi : 10.1016/j.nucengdes.2022.111991.en_US
dc.subjectFuel spheresen_US
dc.subjectHigh temperature gas reactor (HTGR)en_US
dc.subjectLow enriched uranium (LEU)en_US
dc.subjectMulti-group time dependent neutronics and temperaturesen_US
dc.subjectOnce-through-then-out (OTTO)en_US
dc.subjectPebble bed reactor (PBR)en_US
dc.subjectReactor pressure vessel (RPV)en_US
dc.subjectVery superior old program (VSOP)en_US
dc.subject.otherEngineering, built environment and information technology articles SDG-03
dc.subject.otherSDG-03: Good health and well-being
dc.subject.otherEngineering, built environment and information technology articles SDG-04
dc.subject.otherSDG-04: Quality education
dc.subject.otherEngineering, built environment and information technology articles SDG-07
dc.subject.otherSDG-07: Affordable and clean energy
dc.subject.otherEngineering, built environment and information technology articles SDG-09
dc.subject.otherSDG-09: Industry, innovation and infrastructure
dc.subject.otherEngineering, built environment and information technology articles SDG-12
dc.subject.otherSDG-12: Responsible consumption and production
dc.subject.otherEngineering, built environment and information technology articles SDG-13
dc.subject.otherSDG-13: Climate action
dc.titleA comprehensive Thermo-hydraulic neutronic and safety analysis of a 100MWth pebble bed reactor coreen_US
dc.typePostprint Articleen_US

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