Neutronic and thermohydraulic characteristics of a new breeding thorium–uranium mixed SCWR fuel assembly

Three pass core design proposal for a high performance light water reactor

Thomas S. Schulenberg, Jörg Starflinger, J. Heinecke · Progress in Nuclear Energy · 2008 · 82 citations

Engineering, Nuclear Engineering, Reactor Physics +9

Refinement of Transient Criteria and Safety Analysis for a High-Temperature Reactor Cooled by Supercritical Water

Kazuaki Kitoh, Seiichi Koshizuka, Y. Oka · Nuclear Technology · 2001 · 77 citations

Engineering, Nuclear Engineering, Computational Heat Transfer +16

Conceptual design of compact supercritical water-cooled fast reactor with thermal hydraulic coupling

Jaewoon Yoo, Yuki Ishiwatari, Y. Oka et al. · Annals of Nuclear Energy · 2006 · 60 citations

Engineering, Mechanical Engineering, Nuclear Engineering +16

Improved core design of the high temperature supercritical-pressure light water reactor

Akifumi Yamaji, Ken-ichiro F. Kamei, Y. Oka et al. · Annals of Nuclear Energy · 2005 · 58 citations

Engineering, Nuclear Engineering, Process Systems Engineering +10

Pu recycling in a full Th-MOX PWR core. Part I: Steady state analysis

E. Fridman, S. Kliem · Nuclear Engineering and Design · 2010 · 52 citations

Engineering, Nuclear Engineering, Nuclear Fuel Cycle +10