2003
DOI: 10.1016/s0168-583x(03)00453-1
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Experimental benchmarks of the Monte Carlo code penelope

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Cited by 304 publications
(170 citation statements)
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“…These scattering events will cause secondary electron cascades as the energy is dissipated. To quantify this effect and model these processes, the PENELOPE 22,23 Monte Carlo simulation software package for electron/ photon transport was used. The modeling begins by simulating photoelectrons produced at the surface of the modeled sample.…”
mentioning
confidence: 99%
“…These scattering events will cause secondary electron cascades as the energy is dissipated. To quantify this effect and model these processes, the PENELOPE 22,23 Monte Carlo simulation software package for electron/ photon transport was used. The modeling begins by simulating photoelectrons produced at the surface of the modeled sample.…”
mentioning
confidence: 99%
“…We have studied two cases T hot = 50 keV and T hot = 500 keV as representative cases of hot electrons which may be produced in the interaction with matter of nonrelativistic lasers (such as those which can be used in shock ignition experiments [37]) and of hot electrons produced in relativistic interaction with high-intensity lasers, such as those which should be studied in fast-ignition experiments [38]. Using for instance the LIVERMORE [39] or PENELOPE [40,41] physics library, GEANT4 allows simulation of the atomic deexcitation within materials. To investigate the influence of target heating on the Kα and Kβ production, we performed individual simulations for each Z * by using σ K (E; Z * ) and Y (Kα or Kβ, Z * ) presented in the previous section.…”
Section: Influence Of Target Heating On K α and Kβ Observablesmentioning
confidence: 99%
“…General-purpose Monte Carlo codes for radiation interactions have therefore emerged from CERN, Los Alamos National Laboratory and National Research Council Canada. FLUKA [1], MCNP [2], EGSnrc [3], PENE-LOPE [4] and GEANT4 [5], each with distinct design philosophy and development history, serve user communities worldwide. MCNP is particularly elaborate in neutron transport and statistical analysis.…”
Section: Radiation Historiesmentioning
confidence: 99%