The radiological environment at the Mayak PA site and radiation doses to individuals involved in emergency and remediation operations after the 'Kyshtym Accident' in 1957.

This article assesses the radiological environment at the nuclear site of the Mayak PA, Russian Federation, during and after the accident in 1957, the so-called 'Kyshtym Accident', and the radiation doses to those who participated in the eradication of its consequences. Based on numerous archival documents, this paper presents the radiation data for 1957-1960, including individual dosimetry monitoring data and estimated doses to the Mayak workers, as well as the to personnel in supporting organisations and the military involved in the remediation operations. From 1957-1959 some 38 500 individuals took part in the clean-up actions and remediation of contaminated areas of the Mayak PA industrial site after the accident, including individuals exposed at the time of the accident: Mayak PA employees, militarypersonnel, and civil construction workers. External equivalent doses to 10 500 individuals were estimated in the range of 220 to 265 mSv, while there were cases of doses up to 950 mSv and higher. The collective dose received during the accident and its aftermath was in the region of 7300 person-Sv. By October-December 1957, the collective dose was about 4500 person-Sv. Collective doses recorded in 1958 and 1959 amounted to 2250 person-Sv and 480 person-Sv, respectively.

[Biological Dosimetry Technique for Estimation of Doses from Accidental Exposure to External γ-Rays].

Individual doses from external γ-rays were estimated using biological dosimetry based on limited samplings (n1= 15 and n2 12 individuals) which comprised the Mayak workers group with acute radiation sickness (ARS). The following primary data were used for calculation as initial parameters: estimated dose from ex- ternal γ-rays based on physical dosimetry methods - D (Gy); time before first vomiting - T (h); number of lymphocytes in peripheral blood on a second day after acute radiation exposure - L (109/1); number of neutrophils in blood during first hours after accidental radiation exposure - N(109/). A number of mathe- matical models used for dose estimation were verified: power-law dependence of the absorbed dose from ex- ternal γ-rays (D) on time before first vomiting (7), exponential dependence of D on the number of lympho- cytes in peripheral blood (L), dependence of D on the number of neutrophils in peripheral blood (N) and complex models forD association with Tand L parameters as well as-with Tand Nparameters. The biological dosimetry technique based on a complex approach was shown to provide the best agreement with physical dosimetry methods for individual assessment of doses from external γ-rays.

Lung cancer risks from plutonium: an updated analysis of data from the Mayak worker cohort.

Workers at the Mayak nuclear facility in the Russian Federation offer a unique opportunity to evaluate health risks from exposure to inhaled plutonium. Risks of mortality from lung cancer, the most serious carcinogenic effect of plutonium, were evaluated in 14,621 Mayak workers who were hired in the period from 1948-1982, followed for at least 5 years, and either monitored for plutonium or never worked with plutonium. Over the follow-up period from 1953-2008, there were 486 deaths from lung cancer, 446 of them in men. In analyses that were adjusted for external radiation dose and smoking, the plutonium excess relative risk (ERR) per Gy declined with attained age and was higher for females than for males. The ERR per Gy for males at age 60 was 7.4 (95% CI: 5.0-11) while that for females was 24 (95% CI: 11-56). When analyses were restricted to plutonium doses <0.2 Gy, the ERR per Gy for males at age 60 was similar: 7.0 (95% CI: 2.5-13). Of the 486 lung cancer deaths, 105 (22%) were attributed to plutonium exposure and 29 (6%) to external exposure. Analyses of the 12,708 workers with information on smoking indicated that the relationship of plutonium exposure and smoking was likely sub-multiplicative (P = 0.011) and strongly indicated that it was super-additive (P < 0.001). Although extensive efforts have been made to improve plutonium dose estimates in this cohort, they are nevertheless subject to large uncertainties. Large bioassay measurement errors alone are likely to have resulted in serious underestimation of risks, whereas other sources of uncertainty may have biased results in ways that are difficult to predict.

Mayak worker dosimetry study: an overview.

The Mayak Production Association (MPA) was the first plutonium production plant in the former Soviet Union. Workers at the MPA were exposed to relatively large internal radiation intakes and external radiation exposures, particularly in the early years of plant operations. This paper describes the updated dosimetry database, "Doses-2005." Doses-2005 represents a significant improvement in the determination of absorbed organ dose from external radiation and plutonium intake for the original cohort of 18,831 Mayak workers. The methods of dose reconstruction of absorbed organ doses from external radiation uses: 1) archive records of measured dose and worker exposure history, 2) measured energy and directional response characteristics of historical Mayak film dosimeters, and 3) calculated dose conversion factors for Mayak Study-defined exposure scenarios using Monte Carlo techniques. The methods of dose reconstruction for plutonium intake uses two revised models developed from empirical data derived from bioassay and autopsy cases and/or updates from prevailing or emerging International Commission on Radiological Protection models. Other sources of potential significant exposure to workers such as medical diagnostic x-rays, ambient onsite external radiation, neutron radiation, intake of airborne effluent, and intake of nuclides other than plutonium were evaluated to determine their impact on the dose estimates.

Mayak film dosimeter response studies, part I: measurements.

The Mayak Worker Dosimetry study is a joint Russian/U.S. project to evaluate doses received by workers at the Mayak Production Association facilities from 1948-1972. A key investigation in this project is the characterization of responses of the three types of film dosimeters used to monitor workers during this time period. Experimental irradiations of the dosimeters were performed in the radiation calibration laboratories at the National Research Center for Environment and Health (GSF) in Munich, Germany. The irradiations used photon sources from x-ray beams with ten different energy distributions and with Co and Cs isotopic gamma sources. Irradiations were performed with the dosimeters on phantoms and free-in-air. The dosimeters and phantoms were also positioned at varying angles to the radiation beam. The result of the experiments was a thorough characterization of the dosimeter response as a function of photon energy and as a function of angle for energy and angular ranges that cover the conditions encountered in the Mayak workplaces. The characterization data were then available for use in developing correction factors, which could be applied to worker dosimeter readings to provide a more accurate assessment of worker dose and estimates of doses to organs.

Mayak film dosimeter response studies, part II: response models.

A study was performed of energy and angular responses of the film dosimeters that were used for worker monitoring at the Mayak Production Association (Mayak PA) in 1948-1992. The study used experimental data from tests with three types of individual film dosimeters, and the data were used to determine the dosimeters' energy and angular response characteristics in the range from 9 keV to Co energies, with the dosimeters exposed both free-in-air and on-phantom at horizontal and vertical rotation. Mathematical models of the dosimeters were developed to calculate the response characteristics of the dosimeters. The models of the film dosimeters were validated by comparing calculations to measurements. The models were then used as the basis for individual dose reconstruction in realistic photon spectra and worker exposure geometries at the Mayak PA workplaces. Reconstructed individual doses have been included in the Mayak worker database "Doses-2005" that is used for epidemiological studies of the Mayak workers' radiation exposures and subsequent health effects.

Mayak film dosimeter response studies, part iii: application to worker dose assessment.

This paper describes the methods used to correct individual dosimeter readings for workers to obtain estimates of worker doses received at the Mayak Production Association (Mayak PA). Film dosimeters were used at Mayak PA for worker monitoring from 1948 until 1992. The method requires a determination of the relationship between the absorbed dose in film emulsion and the dose in air under calibration conditions, which is then extended to exposures in the actual radiation fields of the workplace. Corrections needed to account for actual workplace exposure conditions were determined by modeling with the Monte Carlo radiation transport computer code MCNP. Correction factors were developed to convert from dosimeter reading to a realistic worker dose. The method was applied as a basis for individual dose reconstruction using film dosimeters in realistic photon spectra and geometries at Mayak PA work areas.

Influence of alpha and gamma radiations and non-radiation risk factors on the incidence of malignant liver tumors among Mayak PA workers.

This Mayak worker-based study focuses on evaluating possible associations between malignant liver cancers and chronic alpha irradiation, chronic gamma irradiation, and non-radiation risk factors (alcohol consumption, smoking, viral hepatitis, chemical exposure, and chronic digestive diseases). This is the first multivariate study related to liver cancer among Mayak workers. The study was performed using the nested, case-control approach and includes 44 cases of malignant liver tumors diagnosed from 1972 to 1999, and 111 matched controls. Adjusted odds ratio (OR(ad)) was evaluated relative to a group of workers with alpha radiation doses to liver (D(alpha)) < 2.0 Gy. Dose estimates of D(alpha) > 2.0 Gy (corresponding (239)Pu body burden estimates >20.4 kBq) were significantly associated (p < 0.003) with the occurrence of hemangiosarcomas (HAS) but only marginal significance (0.05 < p < 0.1) was found for hepatocellular cancers (HCC). The ORad for HAS was 41.7 [95% confidence interval (CI): 4.6, 333] for a group with D(alpha) in the range >2.0-5.0 Gy and was 62.5 (7.4, 500) for a group with D(alpha) > 5.0-16.9 Gy. The attributable risk (AR) was calculated as 82%. For HCC, O(Rad) was estimated as 8.4 (0.8, 85.3; p < 0.07) for a group with D(alpha) in the range >2.0-9.3 Gy. For the indicated group, the AR was 14%. An association with high external gamma-ray doses (D(gamma)) to the total body was revealed for both HCC and for combined liver cancers when dose was treated as a continuous variable. However, we find no evidence that chronic low doses of gamma rays are associated with liver cancer occurrence. Cholangiocarcinoma (CHC) was not associated with either alpha- or gamma-ray exposure. As expected, an association between alcohol abuse and HCC was inferred [O(Rad) = 3.3 (1.2, 9); AR = 41%] but not for CHC or HAS.

[The identification of potential radiation risk groups in case of chronical occupational exposure: individual cancer risks among the industrial firm "Maiak" personnel].

The draft new recommendations of the ICRP emphasize the need for transition from the collective dose to the dose matrix concept with optimization of the radiation protection system. In fact, this means assessment of the attributive (radiation-induced) risk at individual level with allowance for the dynamics of dose accumulation during the whole length of professional experience. The work provides assessments for high potential risk group from the "Mayak" personnel based on the dose matrix and using the UNSCEAR technique for assessing the attributive risk. It was found that about 2% of "Mayak" personnel subject to individual dosimetric monitoring in 2005 can be attributed to this group.

Lung cancer in Mayak workers: interaction of smoking and plutonium exposure.

Lung cancer mortality among 5,058 male workers of the Mayak Production Association has been analyzed with emphasis on the interaction of smoking and radiation exposure by using the two-step clonal expansion (TSCE) model of carcinogenesis. The cohort consists of all Mayak workers with known smoking status, who were employed in the period 1948-1972, and who either had the plutonium concentration in urine measured or who worked in the reactors, where plutonium exposure was negligible. Those who died during the first two years after the first urine sampling were excluded. The follow-up extended until the end of 1998. During this time, 2,176 workers died, including 244 lung cancer cases. Mayak workers were exposed to external (gamma and neutron) radiation, and in the radiochemical and plutonium plants to plutonium. In the preferred TSCE model, internal radiation and smoking act on the clonal expansion of pre-carcinogenic clones. Assuming a plutonium radiation weighting factor of 20, the excess relative risk per lung dose was estimated to be 0.11 (95% CI: 0.08; 0.17) Sv(-1). Most of the lung cancer deaths are found to be due to smoking. The second main factor is the interaction of smoking and internal radiation. The model is sub-multiplicative in relative risks due to smoking and radiation. In a multiplicative version of the TSCE model, internal radiation acts on initiation and transformation rates. This model version agrees with conventional epidemiological risk models, because it also suggests a higher risk estimate than the preferred TSCE model. However, it fits the data less well than the preferred model.

Lung cancer in Mayak workers.

The cohort of nuclear workers at the Mayak Production Association, located in the Russian Federation, is a unique resource for providing information on the health effects of exposure to plutonium as well as the effects of protracted external dose. Lung cancer mortality risks were evaluated in 21,790 Mayak workers, a much larger group than included in previous evaluations of lung cancer risks in this cohort. These analyses, which included 655 lung cancer deaths occurring in the period 1955-2000, were the first to evaluate both excess relative risk (ERR) and excess absolute risk (EAR) models and to give detailed attention to the modifying effects of gender, attained age and age at hire. Lung cancer risks were found to be significantly related to both internal dose to the lung from plutonium and external dose, and risks were described adequately by linear functions. For internal dose, the ERR per gray for females was about four times higher than that for males, whereas the EAR for females was less than half that for males; the ERR showed a strong decline with attained age, whereas the EAR increased with attained age until about age 65 and then decreased. Parallel analyses of lung cancer mortality risks in Mayak workers and Japanese A-bomb survivors were also conducted. Efforts currently under way to improve both internal and external dose estimates, and to develop data on smoking, should result in more accurate risk estimates in the future.

Interaction of radiation and smoking in lung cancer induction among workers at the Mayak nuclear enterprise.

For radiation-related cancer risk evaluation, it is important to assess not only influences of individual risk factors but also their interactive effects (e.g., additive, multiplicative, etc.). Multivariate analysis methods adapted for interactive effects allow such assessments. We have used a multivariate analysis approach to investigate the pair-wise interactions of the previously identified three main etiological factors for lung cancer induction in Russian workers of the Mayak Production Association (PA) nuclear enterprise. These three factors are as follows: (1) body burden of inhaled plutonium-239 (239Pu), an influence on absorbed alpha-radiation dose; (2) cumulative, absorbed external gamma-radiation dose to the lung; and (3) level of cigarette smoking as indicated by a smoking index (SI). The SI represents the cigarettes smoked per day times years smoking. The Mayak PA workers were exposed by inhalation to both soluble and insoluble forms of 239Pu. Based on a cohort of 4,390 persons (77% male), we conducted a nested, case-control study of lung cancer induction using 486 matched cases and controls. Each case was matched to two controls. Matching was based on five factors: sex, year of birth, year work began, profession, and workplace. Three levels of smoking were considered: low (SI = 1 to 499), used as a reference level; middle (SI = 500 to 900); and high (SI = 901 to 2,000). For lung cancer induction, a supra-multiplicative effect was demonstrated for high external gamma-ray doses (> 2.0 Gy) plus high 239Pu intakes (body burden >2.3 kBq). This observation is consistent with the hypothesis of curvilinear dose-response relationships for lung cancer induction by high- and low-LET radiations. The interaction between radiation (external gamma rays or 239Pu body burden) and cigarette smoke was found to depend on the smoking level. For the middle level of smoking in combination with gamma radiation (> 2.0 Gy) or 239Pu body burden (> 2.3 kBq), results were consistent with additive effects. However, for the high level of smoking in combination with gamma radiation (> 2.0 Gy) or 239Pu body burden (> 2.3 kBq), results were consistent with the occurrence of multiplicative effects. These results indicate that low-dose risk estimates for radiation-induced lung cancer derived without adjusting for the influence of cigarette smoking could be greatly overestimated. Further, such systematic error may considerably distort the shape of the risk vs. dose curve and could possibly obscure the presence of a dose threshold for radiation-induced lung cancer.

FISH examination of lymphocytes from Mayak workers for assessment of translocation induction rate under chronic radiation exposures.

PURPOSE: To estimate the translocation-induction rate under chronic exposure conditions by measuring chromosome aberration frequencies in lymphocytes from Mayak nuclear workers using fluorescence in situ hybridization (FISH). MATERIALS AND METHODS: Lymphocytes were examined from 27 nuclear workers at the Mayak Production Association and two control individuals using FISH with probes for chromosomes 1, 2 and 4. Official doses derived from worker film-badge records varied from 0 to 8.50 Gy. RESULTS: The mean (+/-SD) genome-equivalent translocation frequency (F(G)) was 2.30 (+/-0.75)% in the zero-dose group (n = 7), and Poisson regression analysis provided the best-fit equation of F(G)(%) = 2.96(+/-0.39) + 0.69(+/-0.14)D + 0.12(+/-0.05)A, where D is the film-badge-derived dose (Gy), and A is age centred at 67 years. The induction rate would increase to nearly 1% Gy(-1) if the radiation dose to bone marrow, one of the major organs for lymphocytes and where their precursor cells reside, is considered. CONCLUSION: The estimated induction rate in vivo appeared substantially smaller than linear coefficients estimated from various in vitro studies.

EPR dose reconstruction for Russian nuclear workers.

The present paper describes results of the first independent evaluation of the accuracy of the dose-reconstruction technique by electron paramagnetic resonance using tooth enamel. Each of twenty-four teeth donated by Mayak nuclear workers with known occupational radiation exposure histories was cut into two parts so that each tooth could be shared for blind electron paramagnetic resonance examination by at least two of the four laboratories participating in the study. The mean difference (+/- SD) between electron paramagnetic resonance estimates of the paired samples of each tooth shared by the two laboratories in best agreement was 0.02 +/- 0.15 Gy. Mayak workers can be classified into two groups: modern workers (after 1961) having reliable official dose information and earlier nuclear workers whose dose information is less reliable because they were exposed mainly before 1961. Film badges did not contain filters until 1954. Doses in this earlier group are much higher (up to 5 Gy). Comparison of the electron paramagnetic resonance results with tooth doses calculated from official film-badge doses showed a close agreement for the first group, whereas in the second group, official doses appeared to be slightly higher than the electron paramagnetic resonance doses. The results suggested a possibility that the official doses were somewhat overestimated among the high-dose-exposed workers. Consequently, cancer risks derived from this high-dose group might tend to be slightly underestimated.

Verification of occupational doses at the first nuclear plant in the former Soviet Union.

Mean annual occupational exposures are reported for radiation workers at the first Russian industrial nuclear facility 'Mayak', South Ural region, for the period 1948-1988. The underlying individual doses originate from the register of the in-plant radiation safety department and are based on local film dosimetry results. Differentiation is made between personnel working at reactor and radiochemical processing plants. Verification of summed film doses is performed by means of ESR dose reconstruction using extracted teeth from selected individuals. Explanations are given for observed discrepancies between the reconstructed individual doses and original integrated film dosimetry results. The research potential of combined dose information from specific tooth enamel and dentine are shown.