Impact of the introduction of ICRP Publication 103 on neutron dosimetry

Abstract

The impact of the introduction of ICRP Publication 103 on neutron dosimetry was analysed by calculating effective doses in various operational neutron fields, using dose conversion coefficients derived from the recommendations given in ICRP 103 and ICRP 60. It was found from the analysis that effective doses based on ICRP 103 are generally smaller than those based on ICRP 60, mainly owing to the revision of w(R) assigned to neutrons. The results also indicate that H*(10) can provide a conservative estimate for ICRP 103-based effective doses in most neutron fields. These tendencies suggest that the radiological protection system currently adopted in accelerators and nuclear facilities can be maintained after the introduction of ICRP 103, with respect to neutron dosimetry.

Selective contribution of concrete shielding on the equivalent and effective doses in a prostate radiotherapy treatment

“…Table 3 compares effective doses calculated with and without surroundings due to photons and neutrons. Calculations were performed according to the methodology recommended by ICRP 103 (Weiss, 2009;Pujades Claumarchirant et al, 2010;Sato et al, 2011).…”

“…In the calculation of equivalent and effective doses, weight parameters were used for the type of radiation as well as organs and tissues as recommended in ICRP 103 (Weiss, 2009;Sato et al, 2011). The results were normalized relatively to a prostate dose of 1 Gy due to photons.…”