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RISSpecial Issue: EU ESFR-SMART ProjectWord From the Horizon: 2020 EU ESFR-SMART Project Coordinator
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Konstantin MikityukThis Special Issue of the ASME Journal of Nuclear Engineering and Radiation Science includes 2 editorials and 25 technical papers presenting the main achievements of the Horizon-2020 European Union ...
Machine Learning-Based Methodology for Assessment of Doppler Reactivity of Sodium-Cooled Fast Reactor
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: In order to close nuclear fuel cycle and address the problem of sustainability, advanced nuclear reactor systems of the fourth generation are in the focus of the research for many years. With a simple goal of supporting ...
Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Based on feedback from existing reactors and current projects, the European sodium fast reactor-safety measures assessment and research tools (ESFR-SMART) project proposes an optimization of the secondary circuit with the ...
ESFR-SMART Core Safety Measures and Their Preliminary Assessment
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: A large 3600 MW-thermal European sodium fast reactor (ESFR) concept has been studied in a European Horizon-2020 project since September 2017, following an earlier European project. In the paper, we describe new ESFR core ...
Parametric Lattice Study of a Graphite Moderated Molten Salt Reactor
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Molten salt reactors (MSRs) are promising advanced nuclear reactors for closure of the fuel cycle. This paper discusses the core design of graphitemoderated MSRs, thanks to a parametric study of the fuel and moderator ...
Superphénix Benchmark Part I: Results of Static Neutronics
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: In the paper, the specification of a new neutronics benchmark for large sodium cooled fast reactor (SFR) core and results of modeling by different participants are presented. The neutronics benchmark describes the core of ...
Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The objective of this paper is to quantify the coupling effect on the power distribution of sodium-cooled fast reactors (SFRs), specifically the European SFR. Calculations are performed with several state-of-the-art reactor ...