Results 111 to 119 of about 3,167 (119)

Drop Performance Test of Conceptually Designed Control Rod Assembly for Prototype Generation IV Sodium-Cooled Fast Reactor

Nuclear Engineering and Technology, 2017
JongBum Kim
exaly  

Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance

Nuclear Engineering and Technology, 2019
Hoe Woong Kim, JongBum Kim
exaly  

Assessment of ex-core neutron detectors in prototype Gen-IV sodium-cooled fast reactor (PGSFR)

Annals of Nuclear Energy, 2019
Donny Hartanto
exaly  

Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors

Progress in Nuclear Energy, 2019
Dalin Zhang, Tangtao Feng, Shibao Wang
exaly  

Four-bar linkage modeling and kinematics analysis of an in-vessel transfer system for Prototype Gen-IV Sodium-cooled Fast Reactor

Annals of Nuclear Energy, 2018
exaly  

A summary of sodium-cooled fast reactor development

Progress in Nuclear Energy, 2014
exaly  

A NEXT GENERATION SODIUM-COOLED FAST REACTOR CONCEPT AND ITS R&D PROGRAM

Nuclear Engineering and Technology, 2007
exaly  

Experimental Study on Gas Entrainment at Free Surface in Reactor Vessel of a Compact Sodium-Cooled Fast Reactor

Journal of Nuclear Science and Technology, 2008
exaly  

European Commission – 7th Framework Programme

Nuclear Engineering and Design, 2011
exaly