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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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Sodium cooled small fast long-life reactor “4S”
Progress in Nuclear Energy, 2005Abstract CRIEPI and Toshiba Corp. have been exploring to realize a small-sized nuclear reactor for the needs of dispersed energy source and multi-purpose reactor. A conceptual design of 4S ( S uper- S afe, S mall and S imple) reactor is proposed to meet the following design requirements: (1) All temperature feedback reactivity coefficients ...
Nobuyuki Ueda +5 more
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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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Sodium-Cooled Fast Reactors: the ASTRID Plant Project
Revue Générale Nucléaire, 2011ln the framework of the French Act, the 28th of June 2006, about nuclear materials and waste management, an actinides incineration demonstration prototype is to be commissioned in the 2020 decade.CEA has launched this prototype, called ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) to demonstrate the performances and the ...
Pierre Le coz +2 more
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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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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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Sodium Cooled Fast Bread Reactor HCDA Codes Development
Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, 2017Liquid metal fast reactor is one of the Gen IV nuclear power, it is necessary to analyze hypothetical core disruptive accident (HCDA) of FBR to ensure that the system can prevent the radioactive material from leaking out. The modified Bethe-Tait model is the primary method to analyze hypothetical core disruptive accident in the world.
Shi Tai, Zhang Dong-hui, Hu Wen-jun
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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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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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Status of CATHARE 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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