Evaluation of external doses from exposure to gamma sources in the soil using the MCNP code

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Δημοσιευμένα: Δεκ 5, 2019
DOI: https://doi.org/10.12681/hnps.2190
G. Trabidou
Institute of Nuclear Technology-Radiation Protection, NCSR "Demokritos"
I. E. Stamatelatos
Institute of Nuclear Technology-Radiation Protection, NCSR "Demokritos"
P. Kritidis
Institute of Nuclear Technology-Radiation Protection, NCSR "Demokritos"
H. Florou
Institute of Nuclear Technology-Radiation Protection, NCSR "Demokritos"
Περίληψη

Monte Carlo Neutron, Photon transport code (MCNP) was utilized to calculate the external dose from exposure to gamma emitting radionuclides on the ground. The results of the simulation were compared with the experimental data and the results of calculations performed using other analytical methods of estimating external doses from the ground and was found to be in a very good agreement.

Λεπτομέρειες άρθρου
  • Ενότητα
  • Oral contributions (deprecated)
Αναφορές
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