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Physics of Plutonium Recycling : Volume VII: BWR MOX Benchmark - Specification and Results
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ISBN: 1280034599 9786610034598 926429905X 9264199055 Year: 2003 Publisher: Paris : OECD Publishing,

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The OECD/NEA Working Party on the Physics of Plutonium Fuels and Innovative Fuel Cycles (WPPR) conducted a physics code benchmark test for the recycling of plutonium as PuO2/UO2 mixed-oxide (MOX) fuel in boiling water reactors (BWRs) compared to pressurised water reactors (PWRs). This volume reports on the benchmark results and conclusions that can be drawn from it.


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Closed nuclear fuel cycle with fast reactors
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ISBN: 0323993087 0323993095 9780323993098 9780323993081 Year: 2022 Publisher: [S.l.] Academic Press


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Gestion des déchets radioactifs résultant du traitement du combustible irradié
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ISBN: 9264010440 9789264010444 Year: 1973


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Nulear fuel cycle in the 1990s and beyond the century : some trends and foreseeable problems
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ISSN: 00741914 ISBN: 920155589X Year: 1989 Volume: vol 305

Radiological Impacts of Spent Nuclear Fuel Management Options : A Comparative Study
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ISBN: 1280034211 9786610034215 9264182020 9789264182028 9264176578 Year: 2000 Publisher: Paris : OECD Publishing,

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Given its potential significance for public health and the environment, the impact of radioactive releases during important steps of nuclear energy production must be considered when selecting among different fuel cycles. With this in mind, the OECD Nuclear Energy Agency (NEA) has undertaken a comparative study of the radiological impacts of two main fuel cycle options: one with and one without reprocessing of spent nuclear fuel. The study compares the respective impacts of the two options based on generic models and assumptions as well as actual data. It concludes that the difference between them is not significant. A wealth of recent data assembled and evaluated by an international expert team is provided in annex.


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Nuclear energy data 2009 : Donněs sur l'ňergie nuclǎire 2009.
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ISBN: 1282304666 9786612304668 9264047735 9264047727 Year: 2009 Publisher: Paris : OECD : Nuclear Energy Agency,

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This 2009 edition of Nuclear Energy Data, the OECD Nuclear Energy Agency's annual compilation of essential statistics on nuclear energy in OECD countries, provides information on plans for new nuclear construction, nuclear fuel cycle developments and projections of installed nuclear capacity to 2035 in OECD member countries. This comprehensive overview of the current situation and expected trends in various sectors of the nuclear fuel cycle provides authoritative information for policy makers, experts and academics working in the nuclear energy field.

Management of radioactive wastes from the nucleair fuel cycle
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ISBN: 9200202764 9200203760 9789200203763 Year: 1976 Publisher: Vienna International atomic energy agency

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The increased emphasis in many countries on the development and utilization of nuclear power is leading to an expansion of all sectors of the nuclear fuel cycle, giving rise to important policy issues and radioactive-waste management requirements. Consequently, the IAEA and the Nuclear Energy Agency of OECD felt that it would be timely to review latest technology for the management of the radioactive wastes arising from nuclear fuel cycle facilities, to identify where important advances have been made, and to indicate those areas where further technological development is needed. Beginning in 1959, the IAEA, either by itself or jointly with OECD/NEA has held seven international symposia on the management of radioactive wastes. The last symposium, on the management of radioactive wastes from fuel reprocessing, was held jointly by the IAEA and OECD/NEA in Paris in November 1972. An objective of the 1976 symposium was to update the information presented at the previous symposia with the latest technological developments and thinking regarding the management and disposal of all categories of radioactive wastes. Consequently, although the scope of the symposium was rather broad, attention was focussed on operational experience and progress in unresolved areas of radioactive waste management. The programme dealt primarily with the solidification of liquid radioactive wastes and disposal of the products, especially the high-level fission products and actinide-containing waste from fuel reprocessing. Other topics covered policy and planning, treatment of hulls and solvent, management of plutonium-contaminated waste, and removal of gaseous radionuclides. The major topic of interest was the current state of the technology for the reduction and incorporation of the high-level radioactive liquid from fuel reprocessing into solid forms, such as calcines, glasses or ceramics, for safe interim storage and eventual disposal. The approaches to vitrification ranged from two stage processes that first produce a calcine, which then is incorporated into a glass melt, to processes which vitrify the concentrated high-level liquid waste in one step. A novel approach, being investigated at Eurochemic, is the incorporation of a high-level waste calcine into metal matrices


Book
Studies of Intensified Small-scale Processes for Liquid-Liquid Separations in Spent Nuclear Fuel Reprocessing
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ISBN: 3319225863 3319225871 Year: 2015 Publisher: Cham : Springer International Publishing : Imprint: Springer,

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The present work focuses on the development of intensified small-scale extraction units for spent nuclear fuel reprocessing using advanced process engineering with combined experimental and modelling methodologies. It discusses a number of novel elements, such as the intensification of spent fuel reprocessing and the use of ionic liquids as green alternatives to organic solvents. The use of ionic liquids in two-phase liquid-liquid separation is new to the Multiphase Flow community, and has proved to be challenging, especially in small channels, because of the surface and interfacial properties involved, which are very different to those of common organic solvents. Numerical studies have been also performed to couple the hydrodynamics at small scale with the mass transfer. The numerical results, taken together with scale-up studies, are used to evaluate the applicability of the small-scale units in reprocessing large volumes of nuclear waste.

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