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Publications by Yannick Peneliau
Analysis of Dogleg Duct Experiments With 14-MeV Neutron Source Using TRIPOLI-4 Monte Carlo Transport Code
IEEE Transactions on Plasma Science
High Energy Physics
Nuclear
Condensed Matter Physics
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Correlated Production and Analog Transport of Fission Neutrons and Photons Using Fission Models FREYA, FIFRELIN and the Monte Carlo Code TRIPOLI-4® .
EPJ Web of Conferences
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14 MeV Neutron Source for Material Testing
Kakuyūgō kenkyū
The OpenMC Monte Carlo Particle Transport Code
Annals of Nuclear Energy
Engineering
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Measurement and Analysis of Neutron Leakage Spectrum From Nickel Sphere for 14 MeV Neutron Source
Journal of Nuclear Science and Technology
High Energy Physics
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Design and Analysis of Monte Carlo Experiments
FKK Analysis of 14 MeV Neutron-Induced Reactions
Journal of Physics G: Nuclear and Particle Physics
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Design and Analysis of Monte Carlo Experiments
SSRN Electronic Journal
Determination of an Effective Detector Position for Pulsed-Neutron-Source Alpha Measurement by Time-Dependent Monte Carlo Neutron Transport Simulations
Science and Technology of Nuclear Installations
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Radiative Heat Deposition Analysis of Fusion Reactor First Wall by Monte Carlo Transport Code
Journal of Nuclear Science and Technology
High Energy Physics
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Nuclear Energy
