Abstract
To estimate the risks of mixed n-γ radiation fields and to predict the responses of irradiated biological systems, it is essential to obtain a quantitative description of the radiation field or of the energy deposition processes inside an object. For purposes of radiation protection, a rough characterization of the radiation field in terms of type, energy, direction and number of particles is sufficient in most cases. For medical and biological applications, the absorbed dose and the radiation quality have to be determined. The absorbed dose is defined as the quotient of the mean energy imparted by ionizing radiation to the matter in a volume element and the mass of the matter in that volume element.
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Broerse, J.J. (1980). Dosimetry of Neutrons. In: Thomas, R.H., Perez-Mendez, V. (eds) Advances in Radiation Protection and Dosimetry in Medicine. Ettore Majorana International Science Series, vol 2. Springer, Boston, MA. https://doi.org/10.1007/978-1-4757-1715-0_18
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DOI: https://doi.org/10.1007/978-1-4757-1715-0_18
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