Measurements of the 134,137 Cs content in the bodies of the residents of the most contaminated areas of Bryansk and Kaluga oblasts have been performed since 1986. Data which make it possible to evaluate the individual and average effective dose of internal irradiation have been obtained. The work has been supported by calibration and verification of the measurement means and methods. It has been established that the individual dose is described by a nearly log-normal distribution with a long "tail" at doses substantially above the average and median values. This indicates the existence of groups with an elevated radiation risk so that these groups should be treated first when preventative-medical and protective measures are taken.
It is shown that for the most highly contaminated regions of Bryansk and Kaluga oblasts most of the effective dose of internal irradiation is formed over a period of 8-10 years after the accident.Systematic measurements of the 137 Cs and 134 Cs content in the bodies of people living in Bryansk oblast, performed using human radiation monitors and spectrometers, have been conducted since May 1986. Mass examinations have been performed in areas with the heaviest contamination (Novozybkovskii, Zlynkovskii, Krasnogorskii, and Gordeevskii) [1] by specialists from the Bryansk epidemiological and health stations and health protection agencies with the participation of leading scientific and research institutes in the country. Examinations were also performed in 1991 as part of the Russian-German measurement program. The same measurements in the three most highly contaminated areas of Kaluga oblast (Zhizdrinskii, Ul'yanovskii, Khvastovichskii) have been performed since 1986 by the staff of the Medical Radiology Science Center of the Russian Academy of Medical Sciences (MRSC-RAMS) with the participation of specialists from local health agencies and also as part of the Russian-German measurement program [1,2].The goal of the present work was to obtain primary data for evaluating the individual and average effective dose of whole-body internal irradiation for dosimetric support for making decisions concerning preventative-medical, social, and rehabilitation measures directed toward decreasing the consequences of the accident at the Chernobyl nuclear power plant [2]. The present paper presents the main results of the assessments of the effective dose of whole-body internal irradiation which are based on a limited sample of reliable data.Methods and Materials Used for the Investigation. In Bryansk oblast, a Robotron RFT-20046 spectrometer (Germany) with 40 × 40 mm or 63 × 63 mm NaI(Tl) detectors was used first. A transportable spectrometer (with shadow shielding) from the Institute of Biological Physics of the Ministry of Health of the USSR has been used since 1990. Fewer measurements were performed in 1988-1991 than in 1986-1987. At the beginning of the 1990s and in subsequent years,