Results 211 to 220 of about 7,764 (263)

Safety of sodium-cooled fast reactors

Soviet Atomic Energy, 1977
The accumulated experience in the operation of NPP, including those with fast reactors, shows that during normal operation, with due regard for possible operational difficulties and accidents, they ensure a significantly lower level of risk for personnel and the surrounding population than is present in industrial regions and those prone to natural ...
Yu. E. Bagdasarov, L. A. Kochetkov, V. I. Matveev, M. Ya. Kulakovskii, I. A. Kuznetsov, G. B. Pomerantsev, N. V. Krasnoyarov   +6 more
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Instrumentation for Sodium-Cooled Fast Breeder Reactors

Nuclear Science and Engineering, 2013
The 500-MW(electric)-capacity Prototype Fast Breeder Reactor (PFBR) using sodium as a coolant is under construction at Indira Gandhi Centre for Atomic Research, Kalpakkam, India.
Govind Kumar Mishra, M. Sakthivel, S. L. N. Swamy, K. Madhusoodanan   +3 more
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Design challenges for sodium cooled fast reactors

Journal of Nuclear Materials, 2007
It is of vital importance for commercialized fast reactor to achieve component design with excellent integrity and economics. In the phase II of feasibility study till 2005, a system design for commercialized fast reactor for sodium cooling was achieved.
Mamoru Konomura, Masakazu Ichimiya
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Subassembly identification by ultrasound in sodium cooled fast reactors

2018 IEEE International Instrumentation and Measurement Technology Conference (I2MTC), 2018
To prevent fuel handling errors in sodium cooled fast reactors, identifying fuel subassemblies by ultrasound is a method that is being studied. It is based on the reading of a code (aligned notches) engraved on the subassembly head by an emitting/receiving ultrasonic sensor. This reading is performed in sodium with high temperature transducers.
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Status of TRIO_U code for sodium cooled fast reactors

Nuclear Engineering and Design, 2012
Abstract 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, V. Barthel, U. Bieder, F. Ducros, G. Fauchet, C. Fournier, B. Mathieu, F. Perdu, P. Quemere, S. Vandroux   +9 more
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Fuels for sodium-cooled fast reactors: US perspective

Journal of Nuclear Materials, 2007
Abstract 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, Douglas L. Porter, Steven L. Hayes   +2 more
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OPTIMISATION OF SODIUM -COOLED FAST REACTORS

1977
Proceedings 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, 2010
The 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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Status of CATHARE code for sodium cooled fast reactors

Nuclear Engineering and Design, 2012
Abstract 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, R. Baviere, P. Bazin, F. Ducros, G. Geffraye, D. Kadri, F. Perdu, D. Pialla, B. Rameau, N. Tauveron   +9 more
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Investigation on dynamic boiling in sodium cooled fast reactors

Nuclear Engineering and Design, 1970
This 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., Schlechtendahl, E. G., Schultheiss, G. F.   +2 more
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