In 1991, a salvage operation of the waterlogged radioactive contaminated vessel in the water area of lake Ladoga was carried out. In 1953-1954, new radiological weapons or new radiological warfare agenst were tested on this vessel. By the beginning of works, the experimental vessel was on the ooze in the half-flooded condition at a depth of 4,5-6 meters. There were approximate 2000 m3 of contaminated water and silt, mixed with oil products inside the vessel. The aims of the study are to perform:1) the hygienic assessment of radiation situation on the place of the vessel berthing before, during and after ship salvaging; 2) the radiation risk assessment for the population of the region. The assessment of the radiological situation on the board and at the place of the vessel berthing was carried out on the base of dosimetric, spectrometric and radiochemistry surveys. The gamma ray exposure rate at a height of 1 m from the superstructures and main deck outer surfaces was on average 0,14 μSv/h andit did not exceeded 0,30 μSv/h. On the place of the vessel berthing, an increasing of concentrations of Sr-90, Cs-137, Pu-239,240 in samples of water, bottom sediments, and algae has been determined. Object posed no radiation hazard to the population of the region. However, some inhabitants, despite the ban, visited the vessel for recreation and fishing. Their potential exposure dose could reach 0,5 mSv/y. Ship salvaging included salvage pontoon launching, ship’s bottom isolation, liquid waste pumping from the vessel to the special tanker, ship raising and dockage, liquid waste remediation, discharge of remediated water in the water area of lake Ladoga, solidification of liquid waste remained in the vessel’s rooms. Liquid waste remediation and strict radiation control of each process prohibited significant hygienic degradation of the radiation situation in the water area of the lake Ladoga. An insignificant increasing of levels of radioactivity in water during the vessel salvaging was due to the mixing and raising of bottom sediments. For prevention of the environmental contamination by radionuclides and oil-products on the route of the vessel traffic, next protective measures were performed: 1) setting up in the floating dock special pallet wherein collected flowing out of the vessel liquid waste; 2) solidification of liquid waste remained in the vessel’s rooms; 3) partly isolation of the vessel hull.

Temporal variations of radionuclide levels in the epiphytic Usnea sp. lichens from the two islands Sakhalin and Kunashir, the Sakhalin region, Russia have been evaluated using the already published (2011–2013) and new experimental data (2015). A total of 62 lichen samples were measured using high purity germanium γ-ray detectors and multichannel analyzers. In the period 2011–2015, activity concentrations of the anthropogenic radionuclides 134Cs and 137Cs and the natural radionuclides 7Be and 40K were found to be in the range of (<0.53)–41.3, 0.55–50.6, 99–603 and 35–95 Bq kg–1 on dry weight, respectively. The activity concentrations of 134Cs and 137Cs in lichens were statistically significantly higher at Kunashir than at Sakhalin. The present-day levels of radiocesium activity concentrations in lichens are low: < 6 Bq kg–1 for 137Cs and <1 Bq kg–1 for 134Cs. A decline in the annual median 137Cs activity concentrations in lichens from 2011 to 2015 corresponds to a biological half-life of 1.2 y for Kunashir and 1.1 y for Sakhalin. The activity concentrations of 137Cs and 134Cs in lichens were strongly correlated (r=0.978, P<0.01) and the 134Cs biological half-life value of 1.2 y in the period 2011–2013 was similar to the corresponding 137Cs biological half-life value. The soil-tolichens aggregated transfer factor, Tag, for 134Cs at time t=0 after the Fukushima accident is calculated as 0.56 m2 kg–1 at Sakhalin and 0.31 m2 kg–1 at Kunashir. In contrast to radiocesium, the natural radionuclides 7Be and 40K did not show clear time-dependent variations in the Usnea lichens. No correlation was found between 7Be and 40K as well as between 40K and cesium radioisotopes. However, positive and statistically significant (P<0.05) correlations were obtained between 7Be and cesium radioisotopes. High abundance of the Usnea sp. lichens in the study area and large values of Tag for radiocesium in the lichens make these organisms suitable candidates for detection of low levels of airborne radioactive contamination of the environment.

The goal is to determine ionizing radiation natural sources exposure regularities of Altai Territory model areas population. The materials and methods. 11376 radon measurements, 1247 gamma radiation meas-urements in an open area and in residential and office buildings were performed, selection of 189 drinking water tests was carried out. Results. Complex radiation and hygienic examination of the region with the most large municipalities number with model areas allocation was conducted. The assessment of the Altai Territory population’s individual annual radiation doses from natural radionuclides has revealed a number of the regularities depending on the terrain’s ecological and geographical type. Following the research results, ranging the region territories taking into account of annual effective doses of the population from natural sources for 2009-2015 was carried out. The annual individual effective dose of the Altai Territory upland areas population presented by the highest values and ranges from 7.36 mSv / year to 8.19 mSv / year. Foothill regions of Altai and in Salair ridge are characterized by increased population exposure from natural sources. Here the dose ranges from 5.09 mSv / year to 6.22 mSv / year. Steppe and forest-steppe territories are characterized by the lowest level of the natural radiation which is ranging from 3.23 mSv / year to 4.11 mSv / year, that doesn’t exceed the all-Russian levels. Most of the hygienic radon equivalent equilibrium volume activity standards exceedances were registered in mountain and foothill areas buildings. A number of radon anomalies is revealed also in steppe areas. Med exceedances ranged from 203 ± 17.8 Bq / m3 to 480 ± 37.9 Bq / m3. Given the fact that most of these buildings belong to the administrative or educational institutions with an eight-hour working day, the dose of radiation for people there can be up to 10 mSv / year. Conclusion. Spreading of individual annual effective dose of the Altai Territory population showed that five regions of the model areas are converted into three main groups depending on the natural radiation dose due primarily radon equivalent equilibrium volume activity and depends mostly on the eco-geographical terrain type.

In 1949–1956 years, the Techa river was exposed to the intense radioactive contamination, which consequences are not overcome up to now. Currently, the Techa Cascade of Water Reservoirs is the only source of contamination of this river that could be managed. In February 2016 the Chief Executive Officer of the State Corporation “ROSATOM” approved the «Strategic master-plan on the solution of the problems of the Techa Reservoir Cascade» providing a novel look at an issue of remediation of the Techa river. The aim of the article is the implementation of the modern radiation protection system to the existing or potential exposure situations of public residing near the Techa river and an analysis of possible features, events, and processes considered in the longterm forecasts performed in the field of public radiation safety. Although the current radiation state of the Techa River is relatively stable, the task of refining the traditional phenomenological retrospective analysis covering the assessment of the past and current radiation exposure and environmental impacts is considered quite relevant. The Calculation- monitoring complex “TCR-Prognoz” was developed in the framework of the “Strategic Master Plan”. This complex enables to evaluate multivariate scenario calculations resulting in long-term forecasts of radioactive contamination levels in the Techa River and its floodplain, depending on various sets of environmental conditions and anthropogenic factors. Complex radiation surveys to define the detailed character and the time frames of economic activities permitted under the existing radiation safety requirements in the floodplain of the Techa river are recommended to be started after 2020. By this time, the first steady effects associated with the “Strategic Master Plan” implementation will become evident, including those resulting from the efforts aimed at simultaneous minimization of radionuclide discharges into the river under the normal operation of the Techa Cascade of water reservoirs and the potential of the emergency contamination due to its overflow

The article examines radiation and hygienic regulations with regard to the elimination of consequences of the Chernobyl NPP accident in the context of relationships with other aspects, primarily socio-economic and political factors. This experience is reasonable to take into account when defining criteria in other regulatory fields, for example, in radioactive waste classification and remediation of areas. The article presents an analysis of joint features and peculiarities of nuclear accidents in the industry and energy sectors. It is noted that the scale of global consequences of the Chernobyl NPP accident is defined by the large-scale release of radioactivity into the environment, as well as an affiliation of the nuclear installation with the energy sector. Large-scale radiation accidents affect the most diverse spheres of human activities, what, in its turn, evokes the reverse reaction from the society and its institutions, including involvement of political means of settlement. If the latter is seeing for criteria that are scientifically justified and feasible, then the preconditions for minimizing socio-economic impacts are created. In other cases, political decisions, such as nuclear units’ shutdown and phasing out of nuclear energy, appear to be an economic price which society, as a whole and a single industry sector, pay to compensate the negative public response. The article describes fundamental changes in approaches to ensure nuclear and radiation safety that occurred after the Chernobyl NPP accident. Multiple and negative consequences of the Chernobyl accident for human and society are balanced to some extent by a higher level of operational safety, emergency preparedness, and life-cycle safety. The article indicates that harmonization and ensuring consistency of regulations that involve different aspects of nuclear and radiation safety are important to implement practical solutions to the nuclear legacy problems. The development of regulations on criteria for the classification of radioactive waste and the issues of remediation of radioactively contaminated areas are discussed as the examples.

This paper provides review of equipment and methodology for measurement of photon radiation dose; analysis of possible reasons for considerable deviation between the Russian Federation population annual effective external irradiation doses and the relevant average global value. Data on Rospotrebnadzor bodies dosimetry equipment used for measurement of gamma radiation dose are collected and systematized. Over 60 kinds of dosimeters are used for monitoring of population external irradiation doses. Most of dosimeters used in the country have gas-discharge detectors (Geiger-Mueller counters, minor biochemical annunciators, etc.) which have higher total values of own background level and of space radiation response than the modern dosimeters with scintillation detectors. This feature of dosimeters is apparently one of most plausible reasons of a bit overstating assessment of population external irradiation doses. The options for specification of population external irradiation doses assessment are: correction of gamma radiation dose measurement results with consideration of dosimeters own background level and space radiation response, introduction of more up-to-date dosimeters with scintillation detectors, etc. The most promising direction of research in verification of population external irradiation doses assessment is account of dosimetry equipment.

The article is aimed at the hygienic assessment of the sources of utility and drinking water for the Khakasia population regarding radiation protection indicators. The results. Annually over 50% of studied water samples of the utility and drinking water sources for the republic’s population do not comply with the regulatory requirements on specific total alpha –activity ( Aa). This value in the samples varies from 0.03 to 5 Bq/kg. Water samples of utility and drinking water supply sources with the exceedance of limit levels on Alfa – activity were pinpointed in Sorsk, Prigorsk, Verhnyaya Sogra water intake ( Abakan ), Ordzhonikidze, Shirinsk, Bogradsk, Ust’ –Abakan, Altaisk, Beisk, Toshtypsk, Askizsk districts of the republic. For Betaactivity the exceedances of limit levels were not found. High alpha-activity levels are attributed to the natural radionuclides 238U and 234U. On the annual basis water samples from utility and drinking water supply sources display the growing amount of intervention level exceedances on 222Rn. The radon-222 specific activity in the samples varies from 6.0 to 170 Bq/kg. The ratio of the sum of natural radionuclides’ specific activities’ ratios to the corresponding intervention levels is below 1.0 in Ordzhenikidzevsk, Bogradsk, Ust’-Abakan, Shirinsk, Toshtypsk, Askizsk districts, Sorsk town, Prigorsk township, Verkhnaya Sogra water intake ( Abakan ). This means that radiological protection measures are not necessary for those territories in present time. In Beisk and Altaisk districts of the republic, the sum of natural radionuclides’ specific activities’ ratios to the corresponding intervention levels is above 1.0 (the values are in the range of 1.02 – 1.2 ). The average annual individual effective doses for population internal exposure from drinking water natural radionuclides in Khakasia Republic exceed twofold the average levels across Russia. In Beisk and Altaisk districts, the average annual effective dose to the population is in the range from 0.01 to 0.12 mSv/year which exceeds 0.1 mSv/year. In the other administrative districts of the republic, the value is between 0.01 and 0.094 mSv/year. Based on that situation in Altaisk and Beisk districts utility and drinking water supplied to the population is monitored via laboratory control of radiation protection indicators in compliance with the established requirements. The local educational institutions are supplied with bottled drinking water transported from other regions in order to correspond to the quality and protection requirements.

The aim of the study was personnel dose assessment due to the normal operations with the artificial radiation sources. The article is based on the data from the Unified System of Individual Dose Control and Voronezh Region’s radiation-hygienic passport. The data from No.1-DOZ “Information on personnel exposure doses under normal operation of technogenic ionizing radiation sources” and over a period of 2006-2010 years were analyzed. In 2006-2015, the number of organizations, which submitted form No.1-DOZ “Information on personnel exposure doses under normal operation of technogenic ionizing radiation sources”, increased from 175 to 229. In amount of the radiation facilities, Novovoronezh Nuclear Power Plant is the first. Novovoronezh NPP has 1512 sources, which amounts to 51,9% from all sources in Voronezh Region (2915). Health care facilities have 869 radiation sources or 29,8%. X-ray machines are the main part of these sources (844 health care facilities or 97,1% of all medical sources). Industrial sources occupy third place with 305 facilities or 10,5% of all considered sources. In 2015, according to the data from Voronezh Region’s radiation-hygienic passport, the number of “A” group personnel were 4237, the number of “B” group personnel were 2341. The average individual dose for personnel was over the range from 0.66 to 2.02 mSv. Collective dose was from 4.16 to 11.79 man-sieverts per year. The increase of number of the radiation sources has attended with the decrease of individual and collective doses. The most likely it is related to using the modern facilities. In 2015, the maximum value of the average individual dose of “A” group personnel was registered in Voronezh regional hospital (6.17 mSv y–1). There are medical facilities with unsealed and sealed sources in this hospital. In 2006-2015, the average individual doses of personnel of all radiation facilities that use radiation sources in Voronezh region were significantly below the dose limits established by the Radiation Safety Standards NRB-99/2009.

According to results of in-depth studies, the risk of the radiation-induced cataract is higher than it was considered earlier. In April 2011, ICRP released a statement on the tissue reactions. The statement recommends that for the case of for occupational exposure in planned exposure situations, an equivalent dose for the lens of the eye should be less than 20 mSv in a year, averaged over the defined periods of 5 years, with no single year exceeding the value of 50 mSv. In this regard, the new standard IAEA № GSR Part 3 provides the dose limit of 20 mSv in a year for occupational exposure for the lens of the eye. The dosimetric data on levels of exposure for personnel in the Russian Federation is practically absent. This paper performs a preliminary evaluation of equivalent dose for the lens of the eye for personnel working in X-ray operating rooms of medical facilities in Saint Petersburg and Kazan. This group of personnel was selected because of the fact that methodic of carrying out procedures forces medical staff to be not only in the zone of scattered radiation but also in the X-ray beam. This fact significantly increases exposure doses for the personnel. It is shown that actual annual dose can exceed the new dose limit (the highest recorded value Нр(3) in 3 months of work was 8,6 mSv). We made a conclusion on the necessity of the lens of the eye dose monitoring amongst interventional specialists on conditions that new limits will be established in the Russian Federation. The Russian and foreign dosimeters for measurement of individual dose equivalent for the lens of the eye Нр(3) which have been registered in the Russian State Register of Measuring Instruments, are descrivebed in the paper.