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Published in 2018 at "International Journal of Nuclear Energy Science and Technology"
DOI: 10.1504/ijnest.2018.10018234
Abstract: The MCNP code based on the Monte Carlo model is intended for neutron simulations. It is used to study neutron production, neutron flux calculations, energy deposition, dose, and multiplicity of neutrons; in this paper, we…
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Keywords:
neutron production;
spallation neutron;
production;
investigation spallation ... See more keywords