Simulation of industrial 60Со gamma-ray source by Monte-Carlo method
Calculation model developed by means of Monte Carlo code MCNP 4c for 60Со gamma-irradiation source is presented. The simulation of gamma-ray transport in the developed model was carried out. Gamma-ray absorbed doses for different dwell positions were calculated. The distribution of the absorbed dose...
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| Main Author: | |
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| Format: | Article |
| Language: | English |
| Published: |
Institute for Nuclear Research, National Academy of Sciences of Ukraine
2018-09-01
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| Series: | Ядерна фізика та енергетика |
| Subjects: | |
| Online Access: | http://jnpae.kinr.kiev.ua/19.3/html/19.3.0284.html |
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