Status of CATHARE code for sodium cooled fast reactors

Some thermal hydraulic challenges in sodium cooled fast reactors

D. Tenchine · Nuclear Engineering and Design · 2010 · 154 citations

Engineering, Nuclear Engineering, Heat Transfer +13

CATHARE 2 V2.5_2: A single version for various applications

G. Geffraye, O. Antoni, M. Farvacque et al. · Nuclear Engineering and Design · 2010 · 126 citations

Natural Sciences, Computer Science, Electrochemistry +1

Review and proposal for best fit of wire-wrapped fuel bundle friction factor and pressure drop predictions using various existing correlations

E. Bubelis, M. Schikorr · Nuclear Engineering and Design · 2008 · 59 citations

Engineering, Materials Science, Mechanical Engineering +10

Heat transfer in heat exchangers of sodium cooled fast reactor systems

Hiroyasu Mochizuki, Masahito Takano · Nuclear Engineering and Design · 2008 · 54 citations

Engineering, Mechanical Engineering, Nuclear Engineering +13

An Overview of Superphénix Commissioning Tests

J. Gourdon, Bernard. Mesnage, J. L. Voitellier et al. · Nuclear Science and Engineering · 1990 · 30 citations

Engineering, Nuclear Engineering, Instrumentation +11