CRS4 Scheda progetto

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https://hdl.handle.net/11050/60

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Mostra il contenuto di CRS4 Scheda progetto per Autore "Ansaldo Nucleare Spa-Italy-contractor"

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    Central Design Team for a fast-spectrum transmutation experimental facility
    (2009-04-01) Moreau, Vincent; SCK-CEN-Belgium-coordinator; CRS4-Italy-contractor; Nuclear Research and Consultancy Group (NRG)-The Netherlands-contractor; CIEMAT-Spain-contractor; CNRS-France-contractor; ENEA-Italy-contractor; Universitad Politecnica de Valencia-Spain-contractor; Universitad Politecnica de Madrid; AREVA NP SAS-France-contractor; KIT-Germany-contractor; NUTRECK-Republic of Korea-contractor; ITN-Portugal-contractor; Empresarios Agrupados Internacional-Spain-contractor; Oxford Technologies Limited-United Kingdom-contractor; SENES Ingegneria y sistemas SA-Spain-contractor; Forschungszentrum Dresden Rossendorf EV-Germany-contractor; Japan Atomic Energy Agency-Japan-contractor; Del Fungo Giera Energia Spa-Italy-contractor; Adaptive Predictive Expert Control Adex SL-Spain-contractor; Ansaldo Nucleare Spa-Italy-contractor
    Besides the European Global Energy Policy, the European Council adopted an action plan that covers nuclear technologies and supports research in order to "further improve nuclear safety and the management of radioactive waste". To obtain a more efficient and sustainable management of radioactive waste and hence reduce the burden on geological storage, one can apply partitioning and transmutation independently of future commitment or not to nuclear energy. Within European Union many R&D organisations and industries are conducting since a decade strong R&D in the Partitioning &Transmutation (P&T) field with substantial support from the European Commission. Fostering the European efforts towards a major facility realisation would be very beneficial. This will speed up the development and put Europe at lead in this field. The design of a fast spectrum transmutation experimental facility (FASTEF), able to demonstrate efficient transmutation and associated technology through a system working in subcritical mode (ADS) and/or critical mode, is thus the next step after FP6 IP-EUROTRANS. In the vision report of the "Sustainable Nuclear Energy Technological Platform", the need was clearly expressed for a fast-spectrum experimental system to support the development and demonstration of an alternative technology to sodium. Therefore, FASTEF is proposed to be designed to an advanced level for decision to embark for its construction at the horizon of 2012 with the following objectives: to demonstrate the ADS technology and the efficient transmutation of high level waste; to operate as a flexible irradiation facility; to contribute to the demonstration of the Lead Fast Reactor technology without jeopardising the above objectives.
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    European Resarch Programme for the Transmutation of High Level Nuclear Waste in an Accelerator Driven System
    (2005-04-01) Moreau, Vincent; KIT-Germany-coordinator; NRG-The Netherlands-contractor; Centro de investigaciones energeticas, medioambientales y tecnologicas-Spain-contractor; GSI-Germany-contractor; Ansaldo Nucleare Spa-Italy-contractor; Ion Beam Applications SA-Belgium-contractor; Areva NP Gmbh-Germany-contractor; National Nuclear Corporation Limited-United Kingdom-contractor; Del Fungo Giera Energia Spa-Italy-contractor; Advanced Accelerator Applications SA-France-contractor; Tractebel Engineering SA-Belgium-contractor; Oxford Technologies Limited-United Kingdom-contractor; Reseau Europeenne pour l'enseignement du nucleaire-France-contractor; Empresarios Agrupados Internacional SA-Spain-contractor; CRS4-Italy-contractor; INFN-Italy-contractor; Forschungszentrum Dresden Rossendorf EV-Germany-contractor; CSIC-Spain-contractor; Forschungszentrum Juelich-Germany-contractor; INRNE-Bulgaria-contractor; CNRS-France-contractor; Japan Atomic Energy Agency-Japan-contractor; CEA-France-contractor; ENEA-Italy-contractor; Instituto Tecnologico e Nuclear-Portugal-contractor; Paul Scherrer Institute (PSI)-Switzerland-contractor; Joint Institute for Power and Nuclear Research (SOSNY)-Belarus-contractor; UJV-Czech Republic-contractor; Kungliga Tekniska Hoegskolan (KTH)-Sweden-contractor; CEC JRC-Belgium-contractor; Centre d'étude de l'energie nucleaire-Belgium-contractor
    The Integrated Project EUROTRANS (EURopean Research Programme for the TRANSmutation of High Level Nuclear Waste in an Accelerator Driven System) within the ongoing EURATOM 6th European Commission Framework Programme (FP6) is devoted to the study of transmutation of high-level waste from nuclear power plants. The work is focused on transmutation in an Accelerator Driven System (ADS). The objective of EUROTRANS is the assessment of the design and the feasibility of an industrial ADS prototype dedicated to transmutation. The necessary R&D results in the areas of fuel development, structural materials, thermal-hydraulics, heavy liquid metal technology and nuclear data will be made available, together with the experimental demonstration of the ADS component coupling. The outcome of this work will allow to provide a reasonably reliable assessment of technological feasibility and a cost estimate for ADS based transmutation, and to possibly decide on the detailed design of an experimental ADS and its construction in the future. EUROTRANS is integrating critical masses of resources (23M€ EC contribution, 43M€ total eligible costs) and activities of 47 participants from 14 countries, within the industry (10 participants), the national research centres (19) and 17 universities in Europe. The universities are collectively represented by ENEN (European Nuclear Engineering Network). EUROTRANS is the logical continuation of the three FP5 Clusters FUETRA, BASTRA and TESTRA together with the PDS-XADS Project. It takes credit from the Roadmap on P&T of the Technical Working Group [1]. EUROTRANS strengthens and consolidate the European research and development activities in transmutation. The involvement of universities strengthens education and training in nuclear technologies. The involvement of industries assures a market-oriented and economic design development and an effective dissemination of the results.
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    Methodology, Analysis and experiments for the Safety In MYRRHA Assessment
    (2012-11-01) Moreau, Vincent; Studiecentrum voor Kernenergie - Centre d'étude de l'Energie Nucléaire (SCK-CEN)-Belgium-coordinator; ENEA-Italy-contractor; Karlsruher Institut fuer Technologie (KIT)-Germany-contractor; Ansaldo Nucleare Spa-Italy-contractor; Gesellschaft für Anlagen und Reaktorsicherheit MBH (GRS)-Germany-contractor; Nuclear Research and Consultancy Group (NRG)-The Netherlands-contractor; CRS4-Italy-contractor; Kungliga Tekniska Hoegskolan (KTH)-Sweden-contractor; Helmholtz-Zentrum Dresden-Rossendorf EV (HZDR)-Germany-contractor; Regia Autonoma pentru Activitati Nucleare Drobeta Tr. Severin, Sucursala de Cercetari Nucleare Pitesti (INR)-Romania-contractor; Chalmers Tekniska Hoegskola AB (CHALMERS)-Sweden-contractor; National Nuclear Centre (NNC)-Kazakhstan-contractor; Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (CIEMAT)-Spain-contractor
    The Strategic Research Agenda of the EU Sustainable Nuclear Energy Technical platform requires new large infrastructures for its successful deployment. MYRRHA has been identified as a long term supporting research facility for all ESNII systems and as such put in the high-priority list of ESFRI. The goal of MAXSIMA is to contribute to the "safety in MYRRHA" assessment. MAXSIMA has five technical work-packages. The first contains safety analyses to support licensing of MYRRHA. Design-based, design extended and severe accident events will be studied with a focus on transients potentially leading to fuel pin failures. Fuel assembly blockage and control system failure are the least unlikely events leading to core damage. For code validation a thermal-hydraulic study of different blockage scenarios of the fuel bundle and tests of the hydrodynamic behaviour of a new buoyancy driven control/safety system are planned. Both are supported by numerical simulations. Safety of the Steam Generator is treated by looking at consequences and damage propagation of a SG Tube Rupture event (SGTR) and by characterising leak rates and bubble sizes from typical cracks in a SGTR. Additionally a leak detection system and the drag on bubbles travelling through liquid LBE are studied. MOX fuel segment qualification with transient irradiations is a big step in licensing. MAXIMA include validation experiments for safety computer codes involving core damage scenarios with high temperature MOX-LBE interactions. Fuel-coolant-clad chemistry is studied up to 1700°C and a core melt experiment in a reactor is prepared to assess the interaction of LBE with molten fuel. Following the Fukushima accident, effort is put on development of enhanced passive safety systems for decay heat removal and on confinement analyses for HLM systems. A separate work package is dedicated to education and training. Beside workshops, lecture series and training sessions, virtual-safety simulator software will be developed.
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    Thermal hydraulics of innovative nuclear system
    (2010-02-01) Moreau, Vincent; KIT-Germany-coordinator; Commissariat à l´Energie Atomique (CEA)-France-contractor; SCK-CEN-Belgium-contractor; ENEA-Italy-contractor; Nuclear Research and Consultancy Group (NRG)-The Netherlands-contractor; Paul Scherrer Institute (PSI)-Switzerland-contractor; Helmholtz-Zentrum Dresden-Rossendorf EV (HZDR)-Germany-contractor; Kungliga Tekniska Hoegskolan (KTH)-Sweden-contractor; Delft University of Technology-The Netherlands-contractor; UNIPI-Italy-contractor; Università degli Studi di Modena e Reggio Emilia (UniMoRe)-Italy-contractor; UNIBO-Italy-contractor; Ansaldo Nucleare Spa-Italy-contractor; Computational Dynamics Limited (CDAdapco)-United Kingdom-contractor; Jozef Stefan Institute-Slovenia-contractor; Imperial College of London-United Kingdom-contractor; ASCOMP GmbH-Switzerland-contractor; Institut de Radioprotection et de Sûreté Nucléaire (IRSN)-France-contractor; Gesellschaft für Anlagen- und Reaktorsicherheit mbH-Germany-contractor; CRS4-Italy-contractor; Université Catholique de Louvain-Belgium-contractor; Technische Universität München (TUM)-Germany-contractor; Lappeenranta University of Technology (LUT)-Finland-contractor; Texas Engineering Experiment Station (TEES)-United States-contractor
    Thermal-hydraulics is recognized as a key scientific subject in the development of different innovative reactor and transmutation systems. In spite of the difference in coolants (gas, water and liquid metals) and flow channel structures formed by different fuel lattice arrangements, five crosscutting thermal-hydraulic issues are identified and selected in the THINS project, i.e.: advanced reactor core thermal-hydraulics single phase mixed convection single phase turbulence multi-phase flow code coupling and qualification The THINS project focuses on crosscutting issues of thermal-hydraulics encountered in innovative nuclear systems. It brings 24 institutions (23 from European Union) together and synergizes infrastructure available in Europe. The overall objectives of the THINS project are the development and validation of new physical models, improvement and qualification of numerical analysis tools and their application to innovative nuclear systems. Efforts are made to apply the scientific results of this project to education and knowledge-sharing purpose. A large part of the scientific results will have a fundamental relevance in the field of nuclear thermal-hydraulics, nuclear safety and thermal fluid dynamics in general. It is expected that using the results for teaching purposes is highly attractive to strengthen the basis for maintaining and extending know-how in the field.