The core design of ALFRED, a demonstrator for the European lead-cooled reactors

@article{Grasso2014TheCD,
  title={The core design of ALFRED, a demonstrator for the European lead-cooled reactors},
  author={Giacomo Grasso and C. Petrovich and Davide Mattioli and C. Artioli and P. Sciora and Daniela Gugiu and G. Bandini and Evaldas Bubelis and Konstantin Mikityuk},
  journal={Nuclear Engineering and Design},
  year={2014},
  volume={278},
  pages={287-301}
}
Neutronic Analyses of the FREYA Experiments in Support of the ALFRED Lead-Cooled Fast Reactor Core Design and Licensing
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
Preliminary neutron kinetic – thermal hydraulic coupled analysis of the ALFRED reactor using PHISICS/RELAP5-3D
The development of a lead-cooled fast reactor (LFR) demonstrator was proposed, mainly in EU, to investigate the feasibility of an industrial size ELFR (European Lead-cooled Fast Reactor). The
Evolution of the importance of neutron-induced reactions along the cycle of an LFR
The Lead-cooled Fast Reactor is one of the three technologies selected by the Sustainable Nuclear Energy Technology Platform that can meet future European energy needs. Several LFR concepts are now
Coarse-mesh thermal-hydraulics and neutronics coupling for the ALFRED reactor
Among the six advanced reactor systems identified by the Generation IV International Forum, the lead fast reactor (LFR) has been considered as one of the most promising future nuclear power plants.
Simulations of advanced reactor cores in research light water reactor LR-0
Summary of Lead-Cooled Fast Reactor Research
Lead-cooled fast reactor is a fast neutron reactor cooled by liquid lead or lead bismuth alloy. As one of the six main reactors of the fourth generation reactor system, lead-cooled fast reactor can
Test problem for thermal-hydraulics and neutronic coupled calculation fore ALFREAD reactor core
The beginning of a new era of nuclear reactor requires technological advances and also multiples studies. The European Liquid metal cooled Fast breeder Reactor is one of the designs for the
Design of a Nitride-fueled Lead Fast Reactor for Minor Actinides Transmutation
The core design of a 600 MWe lead-cooled, nitride-fueled fast reactor aimed at transmuting MAs is presented. The following major goals are pursued: (i) obtaining a unitary conversion ratio; (ii)
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References

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A CORE DESIGN APPROACH AIMED AT THE SUSTAINABILITY AND INTRINSIC SAFETY OF THE EUROPEAN LEAD-COOLED FAST REACTOR
Among the Generation-IV fast reactor technologies, a Lead-cooled Fast Reactor concept is currently under development in Europe as a potential candidate for the deployment, to meet long-term
Safety Analysis Results of Representative DEC Accidental Transients for the ALFRED Reactor
The conceptual design of the Advanced Lead Fast Reactor European Demonstrator (ALFRED) is under development within the LEADER project to meet the safety objectives of Gen IV nuclear energy systems.
THE ERANOS CODE AND DATA SYSTEM FOR FAST REACTOR NEUTRONIC ANALYSES
TLDR
It is concluded that ERANOS 2.0 can predict the main characteristics of conventional as well as advanced liquid-metal-cooled fast reactors with an excellent accuracy, and that it can also be used for modelling advanced fast reactor cores, source-driven sub-critical media and gas-cooling fast reactors.
The ELSY Project
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