Calculation of age-dependent effective doses for external exposure using the MCNP code
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Tran Van Hung
Abstract
Age-dependent effective dose for external exposure to photons uniformly distributed in air were calculated. Firstly, organ doses were calculated with a series of age-specific MIRD-5 type phantoms using the Monte Carlo code MCNP. The calculations were performed for mono-energetic photon sources with source energies from 10 keV to 5 MeV and for phantoms of newborn, 1, 5, 10, and 15 years-old and adult. Then, the effective doses to the different age-phantoms from the mono-energetic photon sources were estimated based on the obtained organ doses. From the calculated results, it is shown that the effective doses depend on the body size; the effective doses in younger phantoms are higher than those in the older phantoms, especially below 100 keV.
Kurzfassung
Alterabhängige effektive Dosen für externe Exposition durch gleichförmig in Luft verteilte Photonen wurden berechnet. Zunächst wurden Organdosen berechnet mit Hilfe einer Serie von alterspezifischen MIRD-5 Phantomen unter Verwendung des Monte Carlo Rechencodes MCNP. Die Berechnungen wurden durchgeführt für monoenergetische Photonenquellen mit Energien von 10 keV to 5 MeV und für Phantome von Neugeborenen, 1, 5, 10 und 15 Jahre alten Kindern sowie von Erwachsenen. Auf der Grundlage der erhaltenen Organdosen wurden dann die effektiven Dosen für die verschiedenen Phantome und für monoenergetische Photonenquellen bestimmt. Die berechneten Ergebnisse zeigen, dass die effektiven Dosen abhängen von der Körpergröße, wobei die effektiven Dosen in jüngeren Phantomen höher sind als in älteren, insbesondere unterhalb von 100 keV.
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© 2013, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Chemistry aspects of the source term formation for a severe accident in a CANDU type reactor
- Analytical study on degraded core quenching
- Experimental investigations on control of flow instability in single-phase natural circulation loop
- Burnup calculations using serpent code in accelerator driven thorium reactors
- Investigation of neutronic effects in structural material of a hybrid reactor by using the MCNPX Monte Carlo transport code
- Nuclear aspects and cyclotron production of the positron emitter 55Co
- Calculation of age-dependent effective doses for external exposure using the MCNP code
- Effect of Cu2+/Al3+ mole ratio on structure of Cu – Al bimetallic nanoparticles prepared by radiation induced method
- A numerical method for resonance integral calculations
- Computational modeling of monoenergetic neutral particle inverse transport problems in slab geometry
- Effects on criticality of selected scattering phase functions in neutron transport equation using the Chebyshev approximation
- U1 and P1 approximations to neutron transport equation for diffusion length calculation
- Technical Notes/Technische Mitteilungen
- TN approximation for the critical size of one-speed neutrons in a slab with anisotropic scattering
- Albedo and constant source problems for extremely anisotropic scattering
