Conference
Study on Primary and Secondary Heat-Transport Systems for Sodium-Cooled Fast Reactor
Abstract
One of the current engineering challenges is to design next generation (Generation IV) Nuclear Power Plants (NPPs) with significantly higher thermal efficiencies (43–55%) compared to those of current NPPs to match or at least to be close to the thermal efficiencies reached at fossil-fired power plants (55–62%). The Sodium-cooled Fast Reactor (SFR) is one of the six concepts considered under the Generation IV International Forum (GIF) …
Authors
Dragunov A; Saltanov E; Pioro I; Harvel G; Ikeda B
Pagination
pp. v006t16a024-v006t16a024
Publisher
ASME International
Publication Date
July 29, 2013
DOI
10.1115/icone21-16014
Name of conference
Volume 6: Beyond Design Basis Events; Student Paper Competition