Results 191 to 200 of about 2,419,768 (239)
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Status of TRIO_U code for sodium cooled fast reactors
Nuclear Engineering and Design, 2012Abstract Sodium cooled fast reactors (SFRs) have been developed in France for nearly 50 years with successively Rapsodie, Phenix and Superphenix plants. Nowadays, the so-called Astrid prototype is developed in France in the frame of Generation IV deployment.
D. Tenchine +9 more
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Fuels for sodium-cooled fast reactors: US perspective
Journal of Nuclear Materials, 2007Abstract The US experience with mixed oxide, metal, and mixed carbide fuels is substantial, comprised of irradiation of over 50 000 MOX rods, over 130 000 metal rods, and 600 mixed carbide rods, in EBR-II and FFTF alone. All three types have been demonstrated capable of fuel utilization at or above 200 GWd/MTHM.
Douglas C. Crawford +2 more
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OPTIMISATION OF SODIUM -COOLED FAST REACTORS
1977Proceedings of an international conference held on 28 November-1 December 1977 This title is not currently available in print.
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Unanticipated accidents in sodium-cooled fast reactors
Atomic Energy, 2010The definitions and requirements of normative documents for unanticipated accidents at nuclear power plants with fast reactors are analyzed. Definitions are constructed between one another and with a collection of scenarios which can lead to unanticipated accidents, likewise determined by normative documents independently of the probability of these ...
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Investigation on dynamic boiling in sodium cooled fast reactors
Nuclear Engineering and Design, 1970This paper reports on experimental and theoretical investigations of the thermodynamics and hydrodynamics of cooling perturbations in fuel elements of sodium cooled fast reactors. Particular attention is given to bubble nucleation and to growth and shrinkage of the sodium vapour bubble volume.
Peppler, W. +2 more
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Gas entrainment issues in sodium cooled fast reactors
Nuclear Engineering and Design, 2014Abstract Sodium cooled fast reactors have been developed in France for nearly 50 years. The so-called Astrid technology demonstrator is currently designed in the frame of Generation IV deployment. Gas entrainment in the primary sodium circuit is a key issue as it can lead to safety problems in case of accumulation and transport of large quantity of ...
D. Tenchine, C. Fournier, Y. Dolias
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Successive development phases for sodium-cooled fast reactors
Atomic Energy, 2012The development and operation of sodium-cooled fast reactors and the prospects for developing the next generation of such reactors are reviewed. The main phases, the problems of each phase, and the results obtained by solving these problems are shown.
Yu. E. Bagdasarov, A. A. Kamaev
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