OECD Papers

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ISSN: 
1681-2328 (online)
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1609-1914 (print)
http://dx.doi.org/10.1787/16812328
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OECD Papers provides access to a collection of substantive papers not published as books or articles in other OECD series or journals. All subjects are covered, from the latest OECD research on macroeconomics and economic policies, to work in areas as varied as employment, education, environment, trade, science and technology, development and taxation. OECD Papers are available on a subscription basis. Now a part of the OECD Journal

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  15 Nov 2006
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    http://oecd.metastore.ingenta.com/content/0206071ec004.pdf
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NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark
D. Neykov, F. Aydogan, L. Hochreiter, H. Utsuno, F. Kasahara, E. Sartori, M. Martin
The international OECD/NRC BWR Full-size Fine-Mesh Bundle Tests (BFBT) benchmark, based on the NUPEC database, encourages advancement in sub-channel analysis of two-phase flow in rod bundles, which has great relevance with regard to the nuclear reactor safety margin evaluation. This benchmark specification is being designed so that it can systematically assess and compare the participants’ numerical models for the prediction of detailed sub-channel void distributions and critical powers to full-scale experimental data on a prototypical BWR rod bundle. Currently the numerical modelling of sub-channel void distribution has no theoretical approach that can be applied to a wide range of geometrical and operating conditions. In the past decade, experimental and computational technologies have tremendously improved the study of the two-phase flow structure. Over the next decade, it can be expected that mechanistic approaches will be more widely applied to the complicated two-phase fluid phenomena inside fuel bundles. The development of truly mechanistic models for critical power prediction is currently underway. These models must include processes such as void distribution, droplet deposition, liquid film entrainment and spacer grid behaviour. The benchmark specification requires participants to explain their modelling correlations between the measured critical power and the two-phase flow dominant processes.
  15 Nov 2006
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    http://oecd.metastore.ingenta.com/content/0206071ec001.pdf
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French R&D on the Partitioning and Transmutation of Long-lived Radionuclides
OECD
A review has been conducted, at the request of the French Authorities ministère de l’Industrie and ministère de la Recherche, of the first part of the CEA Report 2005 Les déchets radioactifs à haute activité et à vie longue – Recherches et résultats, that is Axe 1 – Séparation et transmutation des radionucléides à vie longue (CEA/DEN/DDIN/2004-642). This review has been organised by the OECD Nuclear Energy Agency (NEA) and carried out by an international review team (IRT) of independent specialists representing all the relevant aspects of chemical partitioning, transmutation and nuclear materials technology. The CEA Report 2005 (the Report) represents a key milestone in the programme of work for which the CEA is responsible under Area 1 of the Law of 30 December 1991 that is "research into solutions enabling long-lived radioactive elements present in waste to be partitioned and transmuted"...
  15 Nov 2006
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    http://oecd.metastore.ingenta.com/content/0206071ec002.pdf
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Safety of Geological Disposal of High-level and Long-lived Radioactive Waste in France
OECD
A review has been conducted of the documentation developed by Andra, collectively known as the Dossier 2005 Argile, by an international review team (IRT) of independent specialists covering all relevant aspects of research, safety assessment, and the geological sciences. As described below, the Dossier represents a key milestone in the programme of work, for which Andra is responsible, to assess the feasibility of the deep geological disposal of high-level and long-lived radioactive waste in France. This report presents the consensus view of the IRT. It is based on the documentation of the Dossier 2005 Argile, but it also draws importantly on information exchanged in writing with Andra in answers to questions raised by the review team, and on direct interactions with staff from Andra during two working seminars in France. Also, in order to fulfil its mandate, the IRT reviewed materials external to the Dossier, namely the document concerning the R&D Programme for a potential new phase of work in the period 2006-2010, in a draft, provisional version.
  15 Nov 2006
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    http://oecd.metastore.ingenta.com/content/0206071ec003.pdf
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VVER-1000 Coolant Transient Benchmark
Boyan D. Ivanov, Kostadin N. Ivanov
In the recent past, the analysis of plant transients and the analysis of reactor core behaviour were performed separately. Usually, the core was represented by a point kinetics model to analyse plant transients and, for the core physics calculations, boundary conditions were imposed at the inlet and the outlet of the core. In reality, these boundary conditions depend on the power generation in the core. To ensure a realistic description of the physical phenomena in an accident analysis, the application of coupled codes is required. In recent years code developers began coupling three-dimensional (3-D) neutron kinetics codes with advanced thermal-hydraulics system codes. Such complex computer codes allow modelling of the entire reactor system, including a 3-D neutronics core. When reactivity initiated accidents with an asymmetric neutron flux distribution in the core are analysed, only such coupled codes are capable of estimating the real feedback effects. These codes can perform safety analyses in order to replace the conservative estimations with best-estimate calculations.
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