Design space exploration for salt-cooled reactor system: Part I – Thermal hydraulic design

Fluoride-salt-cooled High-temperature Reactors (FHRs) are a variant of nuclear reactor offering high power densities and operating temperatures. This paper proposes a new design stream of FHR, leveraging developments and experience from the British Advanced Gas-cooled Reactor (AGR) fleet, the only c...

Full description

Bibliographic Details
Main Authors: Cosgrove, P. (Author), Margulis, M. (Author), Shwageraus, E. (Author), Xing, Z. (Author)
Format: Article
Language:English
Published: Elsevier Ltd 2022
Subjects:
AGR
FHR
Online Access:View Fulltext in Publisher
LEADER 02088nam a2200361Ia 4500
001 10.1016-j.nucengdes.2022.111779
008 220517s2022 CNT 000 0 und d
020 |a 00295493 (ISSN) 
245 1 0 |a Design space exploration for salt-cooled reactor system: Part I – Thermal hydraulic design 
260 0 |b Elsevier Ltd  |c 2022 
856 |z View Fulltext in Publisher  |u https://doi.org/10.1016/j.nucengdes.2022.111779 
520 3 |a Fluoride-salt-cooled High-temperature Reactors (FHRs) are a variant of nuclear reactor offering high power densities and operating temperatures. This paper proposes a new design stream of FHR, leveraging developments and experience from the British Advanced Gas-cooled Reactor (AGR) fleet, the only commercial fleet of high-temperature reactors to-date. The design space for the proposed AGR-like FHR is explored using a thermal-hydraulic simulation and optimisation package, seeking to maximise the reactor's economic performance. Starting from a salt-cooled AGR assembly and applying reasonable thermal-hydraulic constraints, this exploration includes varying the assembly fuel type and geometry, coolant salt, as well as design of the pumps and heat exchangers. Some of the resulting designs promise substantially higher power densities than AGRs and improved economics. © 2022 
650 0 4 |a AGR 
650 0 4 |a Design space exploration 
650 0 4 |a Design spaces 
650 0 4 |a FHR 
650 0 4 |a Fluoride-salt-cooled high-temperature reactor 
650 0 4 |a Fluorine compounds 
650 0 4 |a Gas cooled reactors 
650 0 4 |a High temperature gas reactors 
650 0 4 |a High temperature reactors 
650 0 4 |a High-power-density 
650 0 4 |a High-temperature reactor 
650 0 4 |a Hydraulic optimizations 
650 0 4 |a Operating temperature 
650 0 4 |a Reactor systems 
650 0 4 |a Thermal-hydraulic designs 
650 0 4 |a Thermal-hydraulic simulations 
700 1 |a Cosgrove, P.  |e author 
700 1 |a Margulis, M.  |e author 
700 1 |a Shwageraus, E.  |e author 
700 1 |a Xing, Z.  |e author 
773 |t Nuclear Engineering and Design