Related references
Note: Only part of the references are listed.Research and development of a transient thermal-hydraulic code for system safety analysis of sodium cooled fast reactor
Yang Yu et al.
ANNALS OF NUCLEAR ENERGY (2021)
Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor
B. X. Hu et al.
ANNALS OF NUCLEAR ENERGY (2013)
Transient simulation code development of primary coolant system of Chinese Experimental Fast Reactor
Cui Manman et al.
ANNALS OF NUCLEAR ENERGY (2013)
Dynamic model of Fast Breeder Test Reactor
G. Vaidyanathan et al.
ANNALS OF NUCLEAR ENERGY (2010)