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Some thermal hydraulic challenges in sodium cooled fast reactors
Nuclear Engineering and Design, 2010Sodium cooled fast reactors have been developed in France for nearly 50 years with successively Rapsodie, Phenix and Superphenix plants. Thermal hydraulic challenges have progressively increased with the power and the size of the reactors. After Superphenix stop in 1997, the thermal hydraulic activity on sodium cooled fast reactors was drastically ...
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Nonlinear stability analysis of sodium cooled fast reactors
Nuclear Engineering and Design, 2023openaire +1 more source
Preface to Volume 3: Sodium-cooled fast reactors
2022Masaki Morishita, Hiroyuki Ohshima
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Tritium Transport Analysis in Sodium-Cooled Fast Reactors
2011A tritium permeation analysis code (SFR-TPC) was developed to analyze tritium distributions in Sodium- Cooled Fast Reactors (SFRs) systems. The MATLAB software was used for developing this code. The SFRTPC is based on mass balance equations regarding various chemical forms of hydrogen (i.e. T-, HT, HTO), coupled with a variety of tritium sources, sinks,
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