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    ESFR-SMART Core Safety Measures and Their Preliminary Assessment 

    Source: Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 008 ):;issue: 001:;page 11322-1
    Author(s): Rineiski, Andrei; Mériot, Clément; Marchetti, Marco; Krepel, Jiri; Coquelet-Pascal, Christine; Tsige-Tamirat, Haileyesus; Álvarez-Velarde, Francisco; Girardi, Enrico; Mikityuk, Konstantin
    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 ...
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    Decay Heat Characterization for the European Sodium Fast Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 008 ):;issue: 001:;page 11319-1
    Author(s): Jiménez-Carrascosa, Antonio; García-Herranz, Nuria; Krepel, Jiri; Margulis, Marat; Baker, Una; Shwageraus, Eugene; Fridman, Emil; Gregg, Robert
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In this work, a detailed assessment of the decay heat power for the commercial-size European sodium-cooled fast reactor (ESFR) at the end of its equilibrium cycle has been performed. The summation method has been used to ...
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    Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM 

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 002
    Author(s): Vitullo, Fanny; Krepel, Jiri; Kalilainen, Jarmo; Prasser, Horst-Michael; Pautz, Andreas
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In the pebble-bed high-temperature reactor under construction in China, called the HTR-PM, the spherical fuel elements continuously flow downward in the cylindrical core. The burnup of each pebble is checked at the core ...
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    Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution 

    Source: Journal of Nuclear Engineering and Radiation Science:;2023:;volume( 009 ):;issue: 003:;page 31301-1
    Author(s): Lindley, Ben; Álvarez Velarde, Francisco; Baker, Una; Bodi, Janos; Cosgrove, Paul; Charles, Alan; Fiorina, Carlo; Fridman, Emil; Krepel, Jiri; Lavarenne, Jean; Mikityuk, Konstantin; Nikitin, Evgeny; Ponomarev, Alexander; Radman, Stefan; Shwageraus, Eugene
    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 ...
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