A comprehensive Thermo-hydraulic neutronic and safety analysis of a 100MWth pebble bed reactor core
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Date
Authors
Boyes, W.A.
Slabber, Johan F.M.
Boyes, D.W.
Journal Title
Journal ISSN
Volume Title
Publisher
Elsevier
Abstract
Please read abstract in the article.
Description
DATA AVAILABILITY: Data will be made available on request.
Keywords
Fuel spheres, High temperature gas reactor (HTGR), Low enriched uranium (LEU), Multi-group time dependent neutronics and temperatures, Once-through-then-out (OTTO), Pebble bed reactor (PBR), Reactor pressure vessel (RPV), Very superior old program (VSOP)
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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.