The Laboratory for Neutron Activation Analysis and Gamma Spectrometry at the VŠB-Technical University of Ostrava was equipped with the neutron generator MP320 operating on the principle of the deuterium-tritium fusion and producing 108 neutrons/s at maximum. To ensure radiation protection of radiation workers and public outside the laboratory, the concrete shielding was designed and its protection efficiency was validated by MCNP simulations. Three approaches to calculate the dose rates were compared. The dose rates were estimated for the ORNL MIRD phantom located at the relevant positions (Tally F6 and *F8) and using the MCNPX mesh tally feature with the new ICRP Publication 116 flux-to-dose conversion factors. It was proven that the Approach II in which the absorbed dose rates due to neutrons for all organs are computed using the cell tally F6 and the photon dose calculation is performed by the *F8 energy deposition tally is the most valuable one.
- MeSH
- dávka záření MeSH
- fantomy radiodiagnostické * MeSH
- laboratoře normy MeSH
- lidé MeSH
- metoda Monte Carlo MeSH
- neutronová aktivační analýza přístrojové vybavení normy MeSH
- počítačová simulace MeSH
- radiační ochrana normy MeSH
- radiometrie metody MeSH
- spektrometrie gama přístrojové vybavení normy MeSH
- statistické modely * MeSH
- Check Tag
- lidé MeSH
- Publikační typ
- časopisecké články MeSH
- Geografické názvy
- Česká republika MeSH
- Klíčová slova
- skok na lyžích, modelování, videografická analýza,
- MeSH
- lidé MeSH
- počítačová simulace statistika a číselné údaje MeSH
- pohyb MeSH
- sporty na sněhu statistika a číselné údaje MeSH
- teoretické modely MeSH
- Check Tag
- lidé MeSH
