A comprehensive Thermo-hydraulic neutronic and safety analysis of a 100MWth pebble bed reactor core
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| dc.contributor.author | Boyes, W.A.
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| dc.contributor.author | Slabber, Johan F.M.
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| dc.contributor.author | Boyes, D.W.
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| dc.date.accessioned | 2023-07-18T09:48:47Z | |
| dc.date.issued | 2022-11 | |
| dc.description | DATA AVAILABILITY: Data will be made available on request. | en_US |
| dc.description.abstract | Please read abstract in the article. | en_US |
| dc.description.department | Mechanical and Aeronautical Engineering | en_US |
| dc.description.embargo | 2024-10-01 | |
| dc.description.librarian | hj2023 | en_US |
| dc.description.uri | https://www.elsevier.com/locate/nucengdes | en_US |
| dc.identifier.citation | Boyes, 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.issn | 0029-5493 | |
| dc.identifier.other | 10.1016/j.nucengdes.2022.111991 | |
| dc.identifier.uri | http://hdl.handle.net/2263/91506 | |
| dc.language.iso | en | en_US |
| dc.publisher | Elsevier | en_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.subject | Fuel spheres | en_US |
| dc.subject | High temperature gas reactor (HTGR) | en_US |
| dc.subject | Low enriched uranium (LEU) | en_US |
| dc.subject | Multi-group time dependent neutronics and temperatures | en_US |
| dc.subject | Once-through-then-out (OTTO) | en_US |
| dc.subject | Pebble bed reactor (PBR) | en_US |
| dc.subject | Reactor pressure vessel (RPV) | en_US |
| dc.subject | Very superior old program (VSOP) | en_US |
| dc.subject.other | Engineering, built environment and information technology articles SDG-03 | |
| dc.subject.other | SDG-03: Good health and well-being | |
| dc.subject.other | Engineering, built environment and information technology articles SDG-04 | |
| dc.subject.other | SDG-04: Quality education | |
| dc.subject.other | Engineering, built environment and information technology articles SDG-07 | |
| dc.subject.other | SDG-07: Affordable and clean energy | |
| dc.subject.other | Engineering, built environment and information technology articles SDG-09 | |
| dc.subject.other | SDG-09: Industry, innovation and infrastructure | |
| dc.subject.other | Engineering, built environment and information technology articles SDG-12 | |
| dc.subject.other | SDG-12: Responsible consumption and production | |
| dc.subject.other | Engineering, built environment and information technology articles SDG-13 | |
| dc.subject.other | SDG-13: Climate action | |
| dc.title | A comprehensive Thermo-hydraulic neutronic and safety analysis of a 100MWth pebble bed reactor core | en_US |
| dc.type | Postprint Article | en_US |
