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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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    Neutronic Analyses of the FREYA Experiments in Support of the ALFRED Lead-Cooled Fast Reactor Core Design and Licensing 

    Source: Journal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 001:;page 011402-1
    Author(s): Sarotto, Massimo; Firpo, Gabriele; Kochetkov, Anatoly; Krása, Antonin; Fridman, Emil; Cetnar, Jerzy; Domanska, Grazyna
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: During the EURATOM FP7 project FREYA, a number of experiments were performed in a critical core assembled in the VENUS-F zero-power reactor able to reproduce the ALFRED lead-cooled fast reactor spectrum in a dedicated ...
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    Superphénix Benchmark Part I: Results of Static Neutronics 

    Source: Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 008 ):;issue: 001:;page 11320-1
    Author(s): Ponomarev, Alexander; Mikityuk, Konstantin; Zhang, Liang; Nikitin, Evgeny; Fridman, Emil; Álvarez-Velarde, Francisco; Romojaro Otero, Pablo; Jiménez-Carrascosa, Antonio; García-Herranz, Nuria; Lindley, Ben; Baker, Una; Seubert, Armin; Henry, Romain
    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 ...
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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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