Results 51 to 60 of about 89 (75)

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