Results 31 to 40 of about 8,745 (215)
APPLICATION OF MCNP FOR PREDICTING POWER EXCURSION DURING LOCA IN ATUCHA-2 PHWR [PDF]
, 2012 This thesis consists in the developing and application of a methodology based on MCNP code to predict power and reactivity excursions depending on different representation of physical variables.
PECCHIA, MARCO
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Comparison between GEANT4 and MCNP for well logging applications [PDF]
EPJ Web of Conferences, 2023 MCNP and GEANT4 are two reference Monte Carlo nuclear simulators, MCNP being the standard in the Oil & Gas nuclear logging industry. While performing a simulation benchmark of these two software for the purpose of “Cased Hole” wellbore evaluation ...
Varignier Geoffrey +8 more
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RADIATION DAMAGE AND DPA IN IRON USING MCNP5 [PDF]
European Journal of Materials Science and Engineering, 2020 A Monte Carlo simulation code is developed for the study of neutron induced radiation damage in the materials which results from nuclear collision as well as reactions that create energetic recoil atoms of the host material or reaction creates.
Hiwa Mohammad QADR
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Data-driven discovery of meteotsunami patterns from sparse observations
Environmental Data ScienceMeteotsunamis—tsunami-like sea level oscillations generated by atmospheric disturbances—pose underestimated risks to coastal regions worldwide. Despite growing evidence of their frequency and impact, limited offshore observations and forecasting ...
Ardiansyah Fauzi +4 more
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MCNP calculations of neutron emission anisotropy caused by the GIT-12 hardware
Nukleonika, 2015 The MCNP6 and MCNPX calculations for the GIT-12 device in Tomsk were performed to determine the influence of the gas-puff hardware on the neutron emission anisotropy and the neutron scattering rate.
Šíla Ondřej +4 more
doaj +1 more source
Nuclear waste characterization using Bayesian methods [PDF]
EPJ Web of ConferencesThe relance of the nuclear industrial sector in France is an ambitious plan expected to meet the energy needs of the general public in the 21st century. Along with the construction of new nuclear power plants, advancements are taking place in the fields ...
Chalil Achment +5 more
doaj +1 more source
Brazilian Journal of Radiation Sciences, 2021 MCNP is a code extensively used to simulate experiments involving transport of radiation using the Monte Carlo method. This code allows the study of different geometries, materials, and radiation types (e.g.
Caroline Mattos Barbosa +5 more
doaj +1 more source
, 1997 The Monte Carlo code MCNP-DSP was developed from the Los Alamos MCNP4a code to calculate the time and frequency response statistics obtained from subcritical measurements. The code can be used to simulate a variety of subcritical measurements including source-driven noise analysis, Rossi-{alpha}, pulsed source, passive frequency analysis, multiplicity,
openaire +3 more sources
Medical physics calculations with MCNP: a primer [PDF]
, 2006 The rising desire for individualized medical physics models has sparked a transition from the use of tangible phantoms toward the employment of computational software for medical physics applications.
Lazarine, Alexis D
core +3 more sources