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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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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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