Results 61 to 70 of about 89 (75)

Ultrasonic ranging technique for obstacle monitoring above reactor core in prototype generation IV sodium-cooled fast reactor

Nuclear Engineering and Technology, 2020
Young-Sang Joo
exaly  

On the Safety and Performance Demonstration Tests of Prototype Gen-IV Sodium-Cooled Fast Reactor and Validation and Verification of Computational Codes

Nuclear Engineering and Technology, 2016
Jae-Ho Jeong, Dong-Jin Euh
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
Jae-Han Lee
exaly  

Evaluation of a Sodium–Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor

Nuclear Engineering and Technology, 2016
Kwi-Seok Ha, Won-Pyo Chang, Seok Hun Kang   +2 more
exaly  

Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor

Nuclear Engineering and Technology, 2016
Chan Böck Lee, Jin-Sik Cheon, Jeong-Yong Park   +2 more
exaly  

Fundamental safety strategy against severe accidents on prototype sodium-cooled fast reactor

Journal of Nuclear Science and Technology, 2016
Takaaki Sakai
exaly  

Overview of the SAS4A Metallic Fuel Models and Extended Analysis of a Postulated Severe Accident in the Prototype Gen-IV Sodium-Cooled Fast Reactor

Nuclear Technology, 2020
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, Sung Kyun Kim, Jong-Bum Kim   +2 more
exaly  

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

Nuclear Engineering and Technology, 2017
Jae-Han Lee
exaly  

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

Annals of Nuclear Energy, 2019
Donny Hartanto, Jae-Yong Lim
exaly