TAILIEUCHUNG - SESAME project: advancements in liquid metal thermal hydraulics experiments and simulations

This paper will present the progress in the project with respect to liquid metal cooled reactor thermal-hydraulics (liquid metal heat transfer, fuel assembly thermal-hydraulics, pool thermal-hydraulics, and system thermal-hydraulics). | SESAME project advancements in liquid metal thermal hydraulics experiments and simulations EPJ Nuclear Sci. Technol. 6 18 2020 Nuclear Sciences M. Tarantino et al. published by EDP Sciences 2020 amp Technologies https epjn 2019046 Available online at https REGULAR ARTICLE SESAME project advancements in liquid metal thermal hydraulics experiments and simulations Mariano Tarantino1 Ferry Roelofs2 Afaque Shams2 Abdalla Batta3 Vincent Moreau4 Ivan Di Piazza5 Antoine Gershenfeld6 and Philippe Planquart7 1 ENEA FSN-ING . Brasimone Camugnano Bo 40033 Italy 2 NRG Westerduinweg 3 1755 LE Petten Netherlands 3 KIT Kaiserstr. 12 76131 Karlsruhe Germany 4 CRS4 Science and Technology Park Polaris Piscina Manna 09050 Pula Italy 5 ENEA FSN-ING . Brasimone Camugnano Bo 40033 Italy 6 Commissariat à l Energie Atomique et aux Energies Alternatives CEA Saclay Gif-sur-Yvette cedex France 7 Von Karman Institute for Fluid Dynamics Waterloosesteenweg 72 Sint-Genesius-Rode 1640 Belgium Received 1 July 2019 Accepted 15 July 2019 Abstract. Liquid metal cooled reactors are envisaged to play an important role in the future of nuclear energy production because of their possibility to use natural resources efficiently and to reduce the volume and lifetime of nuclear waste. Sodium and Liquid lead -alloys are considered the short and long term solution respectively as coolant in GEN-IV reactor. Thermal-hydraulics of liquid metals plays a key role in the design and safety assessments of these reactors. Therefore this is the main topic of a large European collaborative program the Horizon 2020 SESAME sponsored by the European Commission. This paper will present the progress in the project with respect to liquid metal cooled reactor thermal-hydraulics liquid metal heat transfer fuel assembly thermal-hydraulics pool thermal-hydraulics and system thermal-hydraulics . New reference data both experimental and high-fidelity numerical data is being generated. And finally .

• Năng lượng
• Reactor thermal hydraulics
• Liquid metal cooled
• Liquid metal heat transfer
• Fuel assembly thermal hydraulics
• System thermal hydraulics
• Tạp chí khoa học
• Khoa học tự nhiên
• Reactor thermalhydraulics
• VVER 1200
• Analysis of Heat Transfer
• Crept pressure tubes
• Inner pitch length modification
• 37 element fuel bundle
• CANDU 6 reactor
• Critical Heat Flux