Sergey I. Rovny

Helmholtz Zentrum München, München, Bavaria, Germany

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Publications (9)3.45 Total impact

  • [show abstract] [hide abstract]
    ABSTRACT: Recently discovered historical documents indicate that large releases of noble gases (mainly (41)Ar and radioactive isotopes of Kr and Xe) from the Mayak Production Association (MPA) over the period from 1948 to 1956 may have caused considerable external exposures of both, inhabitants of Ozyorsk and former inhabitants of villages at the upper Techa River. To quantify this exposure, seven brick samples from three buildings in Ozyorsk, located 8-10 km north-northwest from the radioactive gas release points, were taken. The absorbed dose in brick was measured in a depth interval of 3-13 mm below the exposed surface of the bricks by means of the thermoluminescence (TL) and the optically stimulated luminescence (OSL) method. Generally, luminescence properties using TL were more favorable for precise dose determination than using OSL, but within their uncertainties the results from both methods agree well with each other. The absorbed dose due to natural radiation was assessed and subtracted under the assumption of the bricks to be completely dry. The weighted average of the anthropogenic dose for all samples measured by TL and OSL is 10 +/- 9 and 1 +/- 9 mGy, respectively. An upper limit for a possible anthropogenic dose in brick that would not be detected due to the measurement uncertainties is estimated at 24 mGy. This corresponds to an effective dose of about 21 mSv. A similar range of values is obtained in recently published dispersion calculations that were based on reconstructed MPA releases. It is concluded that the release of radioactive noble gases from the radiochemical and reactor plants at Mayak PA did not lead to a significant external exposure of the population of Ozyorsk. In addition, the study demonstrates the detection limit for anthropogenic doses in ca. 60-year-old bricks to be about 24 mGy, if luminescence methods are used.
    Biophysik 09/2009; 48(4):405-17. · 1.70 Impact Factor
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    ABSTRACT: Brief analysis of design features and operational modes of Mayak PA industrial graphite-uranium reactors (PUGRs) is given. The above mentioned Mayak PA PUGRs determined the rates of releases of radioactive noble gases (RNG) from activation (41Ar) and fission (isotopes of Krypton and Xenon) through the vent stack of the reactor. Information is given on methods and results of experimental determination of RNG atmospheric releases for the period starting from 1965 till PUGRs decommissioning in 1987-1990. A calculation method for reconstruction of radioactive noble gas releases is proposed and justified. The results of reconstruction are given. It is shown that maximum rates of RNG releases from PUGRs high stacks were observed in the 1950s, when ordinary atmospheric air was used as a cover gas for the reactor graphite stacks and gas purification systems (flow-type gas holders) had not been installed yet.
    Radiation Safety Problems, (Special Issue):5-19. 05/2008;
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    ABSTRACT: The article provides the results of reconstruction of external doses to population due to atmospheric releases of inert radioactive gases of activation (41Ar) and fission origin (xenon and krypton isotopes) from the stacks of the “Mayak” PA industrial reactors from 1948 to 1989. Calculation of surface volumetric activities was performed using the RATCHET code. Dose estimate was obtained in a semi-infinite cloud approximation. It is demonstrated that more than 90% of external dose was accumulated from 1948 to 1956. It is established that, generally, the calculation results are in good agreement with archive instrument monitoring data on exposure dose rate and thermoluminescence dosimetry data. External effective doses to the residents of Ozyorsk obtained for different age groups of population with consideration of shielding properties of buildings and duration of time spent outdoors were estimated in the range from 16 to 23 mSv.
    Radiation Safety Problems, (Special Issue):20-31. 05/2008;
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    ABSTRACT: The article describes calculation procedure for reconstruction of radionuclide composition and activity of fission fragments accumulated in the irridated uranium from “Mayak” PA graphite-uranium reactors at the moment, when irradiation is completed, and at the moment, when the uranium is transferred to radiochemical processing (plant B) in the early 1950s. The procedure includes a reactor model and a cooling pool model. It is based on archive data on monthly uranium unloading and loading in the reactor and in the cooling pool of each reactor. The objects of reconstruction include: order of reloading of uranium versus its location radius in the reactor core; duration of irradiation and radionuclide composition of fission fragments for each radius; order of uranium removal from the cooling pool; effective time of uranium storage in the pool; radionuclide composition and activity of fission fragments in the irradiated uranium delivered to radiochemical reprocessing daily and on average for each month. The model is intended for use in reconstruction of parameters of radionuclide release source into the atmosphere and the source of liquid radioactive waste generation at the “Mayak” PA radiochemical plant.
    Radiation Safety Problems, (Special Issue):32-47. 05/2008;
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    ABSTRACT: The method of reconstruction of 131I releases from the Mayak PA Radiochemical Plant stacks for the period from 1948 to 1967 is proposed and the results of reconstruction are given. During this period of time, no continuous routine experimental monitoring of release was performed. As a result, reconstruction was carried out on the basis of earlier obtained data on deliveries of 131I to the radiochemical plants with irradiated uranium from the Mayak PA graphite - uranium reactors. The reconstruction also used calculation - experimental data on the iodine distribution in process solutions and in ventilation exhaust gases from the radiochemical plants, as well as in archive information on the efficiency of iodine trapping with the help of gas purification facilities. Available experimental data on 131I releases from the stacks of the radiochemical plants are given. The reconstruction results are presented as average monthly and annual releases of 131I from the stacks of radiochemical plants B and DB. The results are intended to be used for estimating doses to the population living in the vicinity of the enterprise in the 1950s-1960s.
    Radiation Safety Problems, (Special Issue):48-57. 05/2008;
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    ABSTRACT: The paper provides a short historical overview of creation, usage and current radiation and hydrologic status of the Techa reservoir cascade. The analysis is given of the reservoir water balance, main water flows and sources of radionuclide filtration inflow from the TRC into the open hydrographic system of the Techa river. It is demonstrated that the main problem of the TRC usage is related to the general tendency of water level growth in the reservoirs, which results in the increase of radionuclide inflow into the Techa river with filtration drains and forms additional hydrostatic load on the dam of the end cascade reservoir R-11. Different options increasing safety of the TRC use currently implemented and planned for the future are analyzed.
    12/2007: pages 163-174;
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    ABSTRACT: The Mayak Production Association (MPA) is located in the northern part of Chelyabinsk Oblast. Operating areas are about 10 km from the town of Ozyorsk, the largest populated area nearby, but other nearby populated areas include Novogorny Village, New Metlino Village, and Kyshtym Town. The long-term objective of this (unfunded) project is reconstruction of the time-dependent individual radiation doses to residents of Ozyorsk and the surrounding area from atmospheric releases of radionuclides from the facilities of the Mayak Production Association (MPA). The time period is from 1948 to the present. This information could be used in several epidemiologic studies of the regional population. Two pilotscale studies of thyroid disease among residents of Ozyorsk have found an increase in thyroid nodules among exposed persons compared to unexposed persons and an increase in thyroid carcinoma in Ozyorsk. The success of follow-on studies would depend upon the availability of thyroid doses proposed to be provided. The availability of credible thyroid doses would allow the quantification of risk of thyroid disease and the evaluation of factors such as host susceptibility, age and time effects, and gender differences. Perhaps more importantly, studies of the Ozyorsk residents would not be encumbered with the complications associated with previous early detection screening, as in the Chernobyl studies, or previous medical conditions, as in the I-131 medical studies. The releases to the atmosphere from MPA stacks are a source of exposure to other populations that are the subject of epidemiologic investigation; these populations include the Extended Techa River Cohort (JCCRER Direction 1), the MPA workers (JCCRER Direction 2), and proposed studies of the East Urals Radioactive Trace (EURT) cohort. The doses received by these cohorts from atmospheric releases at the MPA represent a confounding variable that cannot be considered without the information proposed to be provided.
    Biophysik 04/2002; 41(1):33-5. · 1.75 Impact Factor
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    ABSTRACT: This Progress Report for Project 1.4 of the U.S.Russia Joint Coordinating Committee on Radiation Effects Research continues in the abbreviated format of providing details only on the work accomplished during this six-month reporting period.
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    ABSTRACT: The Mayak Production Association (MPA) was established in the late 1940s in accordance with a special Decree of the USSR Government for the production of nuclear weapons. In early years of MPA operation, due to the lack of experience and absence of effective methods of RW management, the enterprise had extensive routine (designed) and non-routine (accidental) releases of gaseous radioactive wastes to the atmosphere. These practices resulted in additional technogenic radiation exposure of residents inhabiting populated areas near the MPA. The primary objective of ongoing studies under JCCRER Project 1.4 is to estimate doses to the residents of Ozersk due to releases of radioactive substances from the stacks of MPA. Preliminary scoping studies have demonstrated that releases of radioactive iodine (131I) from the stacks of the Mayak Radiochemical Plant represented the major contribution to the dose to residents of Ozersk and of other nearby populated areas. The behavior of 131I in the environment and of 131I migration through biological food chains (vegetation-cows-milk-humans) indicated a need for use of special mathematical models to perform the estimation of radiation doses to the population. The goal of this work is to select an appropriate model of the iodine migration in biological food chains and to justify numerical values of the model parameters.