The present paper proposes two methods of calculating components of the dose absorbed by the human body after exposure to a mixed neutron and gamma radiation field. The article presents a novel approach to replace the common iterative method in its analytical form, thus reducing the calculation time. It also shows a possibility of estimating the neutron and gamma doses when their ratio in a mixed beam is not precisely known.

This article describes the application of a simplified Bayesian method for estimation of doses from a mixed field using cytogenetic biological dosimetry, taking as an example neutron and gamma radiation emitted from the MARIA nuclear research reactor in Poland. The Bayesian approach is a good alternative to the commonly used iterative method, which allows separate dose estimation. In the present paper, a computer program, which uses the iterative and simplified Bayesian methods to calculate mixed radiation doses, is introduced.

A new series of dosimetric devices, based on the optically stimulated luminescence (OSL) of BeO, is presented. The dosimetric properties of BeO and the use of OSL are favorable with a linear range at least up to 10 Sv, near tissue energy response, and because of the use of OSL as a measurement technique, the dose information can be re-read. The myOSLraser device combines measurement and zeroing equipment in a single unit and is thus cost and time efficient. The manual reader for single myOSLdosimeters, consisting of two BeO-elements for Hp(0.07) and Hp(10), can be expanded by myOSLautomation, which allows a fully automated analysis of 200 dosimeters. The system exceeds the requirements of EN/IEC 62387. A truly portable handheld device (myOSLchip) allows the manual operation of single element dosimeters, e.g. in phantoms. A simple method is proposed to use the OSL decay signal for the normalization of equipment and bringing into line the sensitivity between instruments.

Without any available physical measurements, absorbed doses of radiation can be assessed through the use of biological methods, of which the most common is cytogenetic biodosimetry. Evaluating the absorbed dose of mixed radiation requires determining the separate doses of each component. This paper aims to test the effectiveness of the Monte Carlo method as an alternate statistical approach for assessing absorbed doses of mixed neutron-γ fields. It combines the iterative method with Bayesian statistics, allowing for evaluation both when the γ to total absorbed dose ratio is known as well as when it is not. Additionally, this paper demonstrates a few of the statistical tests made possible by the Monte Carlo technique, including the distribution of damages among cells.