Hyung-Kook Joo

Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

Jaewoon Yoo, Jinwook Chang, Jae-Yong Lim et al. · Nuclear Engineering and Technology · 2016 · 80 citations · Full text

Engineering, Nuclear Engineering, Systems Engineering +17

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

Chan Bock Lee, Jin-Sik Cheon, Sung Ho Kim et al. · Nuclear Engineering and Technology · 2016 · 31 citations · Full text

Engineering, Materials Engineering, Nuclear Engineering +17

Alternative Applications of Homogeneous Thoria-Urania Fuel in Light Water Reactors to Enhance the Economics of the Thorium Fuel Cycle

Hyung-Kook Joo, Jae-Man Noh, Jaewoon Yoo et al. · Nuclear Technology · 2004 · 20 citations

Engineering, Nuclear Engineering, Nuclear Fuel Cycle +15

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

Jong Bum Kim, Ji-Young Jeong, Tae‐Ho Lee et al. · Nuclear Engineering and Technology · 2016 · 13 citations · Full text

Engineering, Nuclear Engineering, Heat Transfer +16

PBMR Coupled Neutronics/Thermal-hydraulics Transient Benchmark. The PBMR-400 Core Design - Volume 1 The Benchmark Definition

Frederik Reitsma, Kostadin Ivanov, Enrico Sartori et al. · 2013 · 13 citations

Engineering, Nuclear Engineering, Nuclear Safety Analysis +16