Results 151 to 160 of about 2,910 (211)

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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Shape optimization of a sodium cooled fast reactor

SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, 2014
Traditional designs of sodium cooled fast reactors have a positive sodium expansion feedback. During a loss of flow transient without scram, sodium heating and boiling thus insert a positive reactivity and prevents the power from decreasing. Recent studies led at CEA, AREVA and EDF show that cores with complex geometries can feature a very low or even ...
Damien Schmitt, Grégoire Allaire, Olivier Pantz, Nicolas Pozin   +3 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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Gas entrainment issues in sodium cooled fast reactors

Nuclear Engineering and Design, 2014
Abstract 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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A summary of sodium-cooled fast reactor development

Progress in Nuclear Energy, 2014
Abstract Much of the basic technology for the Sodium-cooled fast Reactor (SFR) has been established through long term development experience with former fast reactor programs, and is being confirmed by the Phenix end-of-life tests in France, the restart of Monju in Japan, the lifetime extension of BN-600 in Russia, and the startup of the China ...
Kazumi Aoto, Philippe Dufour, Yang Hongyi, Jean Paul Glatz, Yeong-il Kim, Yury Ashurko, Robert Hill, Nariaki Uto   +7 more
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Sodium cooled small fast long-life reactor “4S”

Progress in Nuclear Energy, 2005
Abstract 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, Izumi Kinoshita, Akio Minato, Shigeo Kasai, Tsugio Yokoyama, Shigeki Maruyama   +5 more
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Successive development phases for sodium-cooled fast reactors

Atomic Energy, 2012
The 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, 2011
ln 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, Jean-François Sauvage, Jean-Pol Serpantie   +2 more
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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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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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