Results 101 to 110 of about 3,167 (119)

Component design and accident analysis of fuel assembly for prototype GEN-IV sodium-cooled fast reactor

Nuclear Engineering and Design, 2018
Abstract The Korea 150 MWe Prototype GEN-IV Sodium cooled Fast Reactor (PGSFR) project has reached the middle of its preliminary safety analysis report (SAR) design phase. The core design studies are being conducted by KAERI. Some design features for the core have been made to comply with the GEN-IV reactor objectives.
K.H. Yoon, H.-K. Kim, H.S. Lee, J.S. Cheon   +3 more
openaire   +3 more sources

NUMERICAL STUDY OF THERMAL STRIPING IN THE UPPER INTERNAL STRUCTURE OF A PROTOTYPE GEN-IV SODIUM-COOLED FAST REACTOR

Journal of Computational Fluids Engineering, 2019
S.R. Choi, D. Kim, Y. Jung, S.K. Choi, J.W. Han   +4 more
openaire   +1 more source

COMPUTATIONAL FLUID DYNAMICS STUDY ON IMPROVEMENT OF THERMAL-HYDRAULIC PERFORMANCE IN THE INTERMEDIATE HEAT EXCHANGER OF A PROTOTYPE GEN-IV SODIUM-COOLED FAST REACTOR

Journal of Computational Fluids Engineering, 2018
S.H. Ryu, Y.S Joo, T.H Lee
openaire   +1 more source

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
Seok Hun Kang, Seung Won Lee, Jae-Ho Jeong   +2 more
exaly  

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

Nuclear Engineering and Technology, 2016
Chan Bock Lee, Jin Sik Cheon, Sungho Kim
exaly  

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

Nuclear Engineering and Technology, 2020
Jong-bum Kim, Young-Sang Joo
exaly  

On the Particle Swarm Optimization of cask shielding design for a prototype Sodium-cooled Fast Reactor

Nuclear Engineering and Technology, 2019
Donny Hartanto
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