Comparison of different computer speeds in calculating of Co 60 depth doses by MCNP4A and MCNP4B Monte Carlo codes
Background and Objective: MCNP is a general-purpose Monte Carlo code that is used for simulating of neutrons, photons and electrons transport in different media. Recently this code has been used for radiotherapy dosimetry and treatment planning. In recent investigations, the reasonable run-time was...
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| Auteurs principaux: | , , |
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| Format: | article |
| Langue: | EN FA |
| Publié: |
Babol University of Medical Sciences
2004
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| Accès en ligne: | https://doaj.org/article/272a19c40c0349859ec3ec33e2cfeb51 |
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