Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor

Neutronics and thermal-hydraulics coupling transient analyses have been carried out to investigate the intrinsic safety characteristics and fuel temperature ranges of a molten chloride salt fast reactor. The analysis system includes a primary heat transport system and a secondary heat transport syst...

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Veröffentlicht in:	Journal of nuclear science and technology 2023-06, Vol.60 (6), p.642-668
1. Verfasser:	Mochizuki, Hiroyasu
Format:	Artikel
Sprache:	eng
Schlagworte:	Chlorides Coupling FLUENT Fluid flow Hydraulics inherent safety Inlet flow Molten salt fast reactor neutronics-thermal hydraulics coupling analysis Nuclear safety RELAP5-3D Transient analysis Transportation systems
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