Liquid Scintillation Spectrometry Research Articles

Long-Range Consequences of Emergency Underground Nuclear Explosions in Yakutia: Incidence of Malignant Neoplasms

The paper evaluates the possibility of interrelation of emergency underground nuclear explosions with an increased incidence of cancer among the population of areas bordering the area of emergency underground nuclear explosions, for example, in Suntarsky and Nyurbinsky districts, in which the incidence of malignant neoplasms, mortality from malignant neoplasms is higher than the average in the Republic of Sakha (Yakutia). For this purpose, the radiation situation of the sites of underground nuclear explosions “Kraton-3” and “Kristall” was investigated: the radionuclide composition of soil and vegetation was studied by semiconductor gamma-ray spectrometry and a water sample by liquid scintillation spectrometry; dosimetric measurements were carried out: the power of exposure doses. Based on the results of water analysis, it is possible to determine the possibility of migration of tritium from the cavities of emergency underground nuclear explosions. The results of the study of vegetation and soil showed the presence of artificial radionuclides 137Cs, 241Am and traces of 60Co. High values of the specific activity of radiocesium are observed in several samples taken near the area “Kraton-3”. Also in this area, the results of dosimetric measurements showed a slight decrease in the gamma background level, but which still remains elevated and exceeds the safe level by 2.5 times. It is possible that the increased incidence rate in the districts of the republic bordering the area of emergency underground nuclear explosions can be considered as their long-term consequences due to additional dose loads, for example, from caesium during the entire time after the explosions, since the half-life of caesium is approximately 30 years. The results of this study can be considered as a basis for the development of recommendations, possible regulations that can be applied in the implementation of compliance with radiation safety standards during future similar tests and during mining, during which there may be emissions of natural radionuclides to the earth's surface.

Determination Of Heavy Metals and Radon Concentration in Soil and Water Samples from Wadi-B Jere Oil Exploration Sites in Maiduguri, Northeast Nigeria

Radon gas and heavy metals are two significant risk factors that can cause lung cancer. Wadi B, a locality in Jere local government of Borno state, is an area where oil exploration is underway. There is a potential health risk of contamination of the drinking water and soil samples in the area. To investigate radon concentration and heavy metal contamination, several samples of water from wells and boreholes, as well as soil samples, were collected for analysis. The analysis was conducted using liquid scintillation (LSC) and atomic absorption spectrometry. The result of radioactivity analysis using LSC shows that water samples have varying levels of radon concentration ranging from 17.77 Bql-1 to 22.50Bql-1 which exceeded the maximum contaminant levels of 11.1Bq/L set by the USEPA 1999 and the world average value of 10Bq/L set by the World Health Organisation (WHO 2004). The mean annual effective cancer risk of radon intake varied across sampling points, ranging from 0.164, 0.246, 0.287 to 0.130, 0.218, and 0.227 for adults, children, and infants, respectively, with mean values of 0.146, 0.219, and 0.255. The mean values of excess lifetime cancer risk (ELCR) associated with radon inhalation and ingestion for adults, children, and infants were 0.0005110, 0.0007660, and 0.0008930, respectively. Moreover, elevated conductivity and total dissolved solids in water samples suggest potential contamination, exceeding the recommended limits set by the World Health Organization. On the other hand, Heavy metals analysis shows a mean value of ELCR 0.125009 for adults and 0.000063 for infants. Results showed that heavy metal concentrations in soil samples exceeded permissible limits for all metals except chromium and lead, with the order of concentration being Cr < Cd < Pb < Cu < Zn. These findings underscore the need for ongoing monitoring and remediation efforts to mitigate environmental and health risks in Wadi B

Detritiation of the Organic Material in the MSO Process

Tritium is a radioactive isotope of hydrogen, and due to its limited supply and related high price, it is necessary to recover it from tritiated materials via detritiation technologies. The number of tritiated materials arises during fusion. Tritium from fusion reactors is deposited in the outer layer of plasma-facing materials, which must be dealt with during maintenance or decommissioning processes. A second source of waste is laboratory equipment that could be contaminated with tritium. High-temperature treatment in an oxidation environment can achieve the release of tritium from metals or organic materials. The tritiated vapor is then captured in a series of water bubblers and reprocessed into pure T2. One of the high-temperature methods is molten salt oxidation (MSO), which uses high temperatures, alkaline salt, and an oxidative environment for flameless oxidation of different types of waste. This work aimed to simulate the detritiation processes of tritiated organic materials in MSO technology. First, a series of experiments with D2O absorbed in ion resins was conducted. The organic waste was decomposed within the molten salt, and the flue gas was measured to determine the oxidation efficiency. The D2O was captured in a series of water bubblers, and the water was then analyzed with attenuated total reflectance (ATR)–Fourier transform infrared spectroscopy (FTIR). The results showed that all deuterium in the form of D2O was caught in the first water bubbler. The capture efficiency ranged from 22.32% to 61.13%. The lower efficiency capture can be explained as D2O in water can form a HDO molecule and its correct determination is problematic. The second type of experiment was carried out with T2O with an activity of 851 Bq and with tritiated oil with an activity of 2495 Bq. The T2O was added to the set amount of ion resins and dosed into MSO. A peristaltic pump dosed the tritiated oil. The flue gas was measured to determine oxidation efficiency, and the T2O was captured within the water bubblers. The water was analyzed with liquid scintillation spectroscopy. The capture efficiency ranged between 76.42% to 97.87%. The results showed that this technology is suitable for the detritiation of tritiated organic materials.

Assessment of Radioecologically Relevant Radionuclides 14C, 99Tc, and 129I in Vitrified High-Level Nuclear Wastes from Spent Fuel Reprocessing

A method is proposed for quantifying the specific activities of radioecologically significant radionuclides, including 14C, 99Tc, and 129I, in vitrified high-level wastes. The conditions for the separation and purification of these radionuclides from potential interfering components are optimized and the yield coefficients and purification factors are determined. The quantification of 14C entails a three-fold distillation in CO2 followed by the measurement of the 14C counting rate in the purified solution by liquid scintillation spectrometry. 129I was determined by dissolving a sample in HNO3, five-fold extraction, and the subsequent measurement of the 129I counting rate in the purified solution using liquid scintillation spectrometry. The determination of 99Тс included dissolving a sample in the presence of ClO–, double extraction-chromatographic separation of 99Тс with an adsorbent impregnated with methyltrioctylammonium nitrate, followed by the determination of its activity by inductively coupled plasma–mass spectrometry. We have applied this approach to a simulator of vitrified high-level waste, labeled with radionuclides, and achieved satisfactory results. This approach will be instrumental in the analysis of the accumulated vitrified high-level wastes at the “Mayak” Production Association (Mayak PA). The results will be important for modeling the engineering safety barriers of a deep disposal site for radioactive wastes.

Investigation of the Influence of Ionization Radiation on Glassy Carbon Coatings, after Long Stay in the Outer Space on the International Space Station (ISS)

In this study two types of samples of spectrally pure graphite, compacted and coated with glassy carbon, were analyzed with liquid scintillation spectrometry, scanning electron microscopy (SEM) and X-ray diffractometry (XRD). “Space” sample has been sent in outer space on the surface of ISS for 28 months. “Space” sample is compared with “reference” sample, made of the same material, but stored on Earth for the same period.
 Radiation environment data were collected using R3DR2-Lyulin instrument, located in the outer space very close to the samples, in the same module of ISS. The effect of cosmic radiation leads to slight increase of 14C content, detected by liquid scintillation spectrometry.
 SEM and thermal test using XRD did not show any noticeable changes in terms of structure and phase composition. This confirms the high degree of reliability of this material under significantly milder operating conditions in Earth orbit.

Towards a radon-in-water primary standard at LNHB

Despite widespread radon-in-water measurements, no primary radon-in-water standards currently exist. This work aims to bridge this gap by developing a system to produce radon-in-water reference materials. The system relies on cryogenic, loss-free transfer of radon, which is standardized through defined solid angle measurements, to a radon standard in water. It allows for preparation of liquid scintillation and gamma-ray spectrometry samples with traceable radon-in-water concentrations. The system's design, functionality, and the results of pilot performance tests are described.

Quality Assurance of Potential Radioanalytical Methods for 14C in Environmental Samples

Today, the measurement of 14C in environmental samples is of particular interest, as it enables the assessment of the impact caused by nuclear activities and the fossil fuel industry on the environment. In order to assure the quality of 14C measurement results, the strategy to enlarge the validation of three radioanalytical methods in environmental samples using liquid scintillation spectrometry—the direct counting of water, bubbling of water and combustion of solids—is presented. Due certain difficulties, such as the lack of quality control materials and the scarcity of proficiency test and intercomparison exercises, especially in solid samples, a set of water and soil samples were prepared for the purpose by tracing them with known quantities of a 14C standard solution at two activity levels. Aliquots were subjected to the corresponding method and their activity concentration was calculated. Finally, uncertainty, detection limit, accuracy, precision, repeatability and linearity were analysed. The acceptance criteria for the quality parameters were previously established according to ISO 13528:2015 standard and Eurachem Laboratory Guide to Method Validation. In all the methods, the studied parameters fall within the acceptance range, so they are validated. The quality of the results in real samples is controlled through field validation.

РАСПРОСТРАНЕНИЕ УГЛЕРОДА-14 В ОКРУЖАЮЩЕЙ СРЕДЕ ПРИ НОРМАЛЬНЫХ УСЛОВИЯХ ЭКСПЛУАТАЦИИ КУРСКОЙ АЭС

Introduction: 14C is one of the fifteen radionuclides that account for at least 99 % of the radiation dose to the critical group of the population from NPP emission sources. The continuous growth of the total capacity of operating NPPs leads to a significant increase in the amount of 14С emitted into the environment during NPP operation. Efficient capture and disposal of 14C, which has a half-life of 5760 years, is a very laborious undertaking. At the same time, due to the high mobility of this radionuclide, local foci of contamination with 14C can appear both near the NPP at a distance of 1–2 km from its ventilation pipe, and in soil and plants located at a distance of 20–30 km from the NPP due to the transfer of air masses. Therefore, the control of the formation of 14C during the operation of nuclear power plants, its content in emissions and discharges of nuclear power plants, as well as distribution in the environment is an urgent problem today. Purpose: Analysis of the environmental pollution due to emissions and discharges of radiocarbon from the Kurskaya nuclear power plant. Material and methods: During the research, a method being developed by specialists of the Laboratory for Radiation Safety of Personnel was used to determine the specific activity of 14C in soil and vegetation. To explore the 14C content in the air, the method of bubbling air through a TASC-HT-HTO-C-14 flow meter-sampler (Overhoff technology, USA) and the method of air conditioning through a Ballu BDH-15L air dryer (Ballu, Russia) were used. To prepare counting samples from selected soil and food samples, a method based on the combustion of selected samples in a Pyrolyser-6 Trio catalytic decomposition system was used. All prepared counting samples, including samples from surface water and biosubstrate of the personnel of the Kursk NPP and the population, were measured by liquid scintillation spectrometry on a Tri-Carb 3180 TR/SL alpha, beta spectrometer. Results: On the basis of an integrated approach to assessing the content of 14C in air, water, soil and food, an analysis of the formation of environmental pollution due to emissions and discharges 14C from the Kurskaya NPP was carried out. Conclusions: An increased content of the 14C radionuclide in soil samples, food products and vegetation in the area of the Kursk NPP with RBMK-1000 nuclear reactors is shown, both in comparison with the content of natural 14C and NPPs operating BN-600,800 and VVER-1000 nuclear reactors. The necessity of taking into account radiocarbon emissions from NPPs into the environment in the problem of optimizing the radiation protection of the population under the conditions of normal operation of NPPs is confirmed.

CHARACTERISTICS OF PINE NEEDLES EXPOSED TO MULTI-SOURCE POLLUTION IN SILESIA: RADIOCARBON CONCENTRATION IN PINE NEEDLES AND ELEMENTAL ANALYSIS OF THE NEEDLES’ SURFACE DEPOSITS

ABSTRACTWe present here the analysis of the radiocarbon concentration and the components deposited on 2-year-old Pinus sylvestris L. needles collected in 2021, which were exposed to air contaminants for approximately two years. The needles were collected from seven sampling sites located near roads, households, and industrial factories in Silesia, the most industrialized part of Poland. The radiocarbon concentration was investigated using liquid scintillation spectrometry. Scanning electron microscopy and energy-dispersive X-ray spectroscopy were used to quantitatively analyze the elements deposited on the surface of pine needles. The depletion of the radiocarbon concentration in pine needles relative to clean air was observed at most of the investigated sites. Although it has been observed that in the research area, the fossil fuel CO2 emission ranging from 0.4 to 3%, we cannot exclude that Suess effect may be underestimated due to biomass burning and mixing of the 14CO2 origin from different sources. A significant amount of silicon, nitrogen, and sulfur was commonly found in samples, Metal elements of Ca, Fe, Al, Mg, and K were also present in most samples. Heavier elements of Fe and Ti were present in higher concentrations only in needles obtained from sites nearer to the heat and power plant in Łaziska Górne.

Quantification of excess Carbon-14 specific activity in terrestrial biota in the off-site locations of the PHWR nuclear power plant at Kaiga, India

This is the first detailed study on 14C activity in the environment surrounding a nuclear facility in India. Samples of food matrices and wild plants from the off-site locations of the PHWR nuclear power plant (NPP) at Kaiga were analysed by liquid scintillation spectrometry, results were validated by accelerator mass spectrometry, and an extensive database (N = 142) was established. The stable isotope ratio of carbon (δ13C) in terrestrial plants varied from −33.5 to −23.3 ‰. The maximum excess 14C activity recorded in terrestrial biota was 44 Bq kg−1C (19 pMC). About 75 % of the samples exhibited specific activity in the range 228–249 Bq kg−1C (101–110 pMC). Statistical tests on the 14C specific activity dataset for 2.3–5, 5–10, and 10–20 km radial zones confirmed that the impact of the operation of the NPP on the environment beyond 5 km is minimal. The study suggests that the 14C activity released through gaseous effluents from Kaiga NPP is transported to greater distances along the axis of the valley than that predicted by the Gaussian plume model and those reported for other NPP sites worldwide. This is due to the unique topography of the Kaiga valley in which wind flow channelling, strong winds in the valley mouth, and calm wind within the valley due to the blocking effect by hills for the south-westerly wind regime play dominant roles in the transport of gaseous effluents. The 14C specific activity values at upwind monitoring stations located at >5 km distance from the NPP during the south-westerly wind regime were higher than those observed during the north-easterly wind regime when the same monitoring stations were located on the downwind side. The ingestion dose to the population in the 2.3–5 km radius zone, attributable to the release of 14C from the NPP, was 0.75 μSv y−1. This is a negligibly small fraction of the ICRP recommended dose limit of 1000 μSv y−1 for the public from other than natural sources. The dose due to the natural 14C activity in the Kaiga region was 12 µSv y-1, corresponding to the ambient natural activity of 230 Bq kg-1 C.

Determining the amounts of organically bound tritium and radiocarbon using a combined preparation step and liquid scintillation spectrometry

Determining the amounts of organically bound tritium and radiocarbon using a combined preparation step and liquid scintillation spectrometry

Preliminarily Experiments of Liquid Scintillation Cocktail Waste Solidification

Liquid scintillation spectroscopy (LSC) is a widely used laboratory method for measuring radioactive especially low-energy alpha and beta emitter isotopes in solutions. Since the scintillation cocktails (SCs) contain large amounts of aromatic hydrocarbon compounds after the LSC measurement, the sample usually becomes organic radioactive waste, which is challenging to manage and dispose of. The most common and effective waste treatment method is incineration, a costly and cumbersome solution. Another simpler and less expensive way is the immobilization the organic liquids by embedding in cement or geopolymer matrix.The aim of our experiments is to find a universal mix design to solidify and immobilize scintillation cocktail wastes (SCWs) of unknown composition. During the measurement, we assumed that the SCWs could contain Ultima Gold, Ultima Gold LLT, InstaGel Plus and ProSafe FC type scintillation cocktails in pure form or mixed with unknown quantities of water. Therefore, we performed experiments with inactive pure SCs as surrogates to mimic the SCWs. Since the water content determination of the organic solutions is difficult, the mix design must be independent of the water content of SCWs.During our experiments, we found an appropriate mix design to solidify all available SCs up to 5% using CEM I 42.5 N type cement, Metaver N type metakaolin and sodium hydroxide. We could solidify our tested SCW with this mix, and this product meets the waste acceptance criteria of all Hungarian radioactive waste repositories.

Method validation for determination of 14C with the use of CO2 absorption method

The CO2 absorption method is applicable for analyzing radiocarbon content in environmental samples. Since this method is characterized with low accuracy and sensitivity, optimization and improvement are needed. In the Laboratory for Liquid Scintillation Spectrometry at Jožef Stefan Institute, internal method validation was performed. The main aim of this validation was to set optimal and controlled conditions that would improve the total uncertainty. For that purpose, we investigated the effect of three parameters on the final results: size of the trap, flow rate and combination of trapping mediums. All measurements were performed on ultra-low level liquid scintillation counter Quantulus™ 1220. The counting efficiency was determined with the use of the external standard method (SQP(E)) and standard addition method. We recognized the use of a big trap, thus use of a balance with a readability of 0.01 g, as the most significant contributor to the total uncertainty. A small trap, flow rate of 0.1 L/min and a mixture of CarbonCount™ and CarbonTrap™ proved to be the most suitable parameters. Using a small trap instead of a big one lowered the relative uncertainty from 2.4% to 0.01%, causing a decrease in the total uncertainty from 4.7% to 3.2%.

The 24th international conference on advances in Liquid Scintillation Spectrometry (LSC2020), October 18–20, 2021, Shenzhen, China

The 24th international conference on advances in Liquid Scintillation Spectrometry (LSC2020), October 18–20, 2021, Shenzhen, China

Development of a rapid technique for sequential separation of plutonium/americium in nasal swab using solvent extraction and liquid scintillation spectrometry

A rapid radiochemical method has been developed for estimation of plutonium and americium in nasal swab using extractive liquid scintillation spectrometry. The method involves solvent extraction of plutonium and americium from pre-treated nasal swab using 0.2 M Di-(2-ethylhexyl)phosphoricacid prepared in toluene scintillator & back extraction of americium in aqueous phase using 0.35 M HNO3. Activity assessment was carried out using liquid scintillation spectrometry. Overall recovery obtained was 96% for plutonium and 76% for americium with a sample turnaround time of 3 h.

TRPC5OS induces tumorigenesis by increasing ENO1-mediated glucose uptake in breast cancer

Breast cancer is the most common malignant tumor worldwide and the leading cause of cancer-related deaths in female. Metabolic reprogramming plays critical roles in breast tumorigenesis and induces enhanced glucose uptake and glycolysis. TRPC5OS is encoded by short transient receptor potential channel 5 opposite strand, and predicted to correlate with tumor metabolic reprogramming. Here we aim to elucidate the function of TRPC5OS in aberrant metabolism mediated tumorigenesis. We detected TRPC5OS expression levels in cell lines and tissues by quantitative real-time polymerase chain reaction and immunohistochemistry. Then we assessed the effects of TRPC5OS on proliferation and cell cycle progression in breast cancer cells by cell counting kit-8, colony-formation, EdU-incorporation assays and flow cytometry. Tumor growth in vivo was observed in a mouse xenograft model. Mass spectrum analyses were performed to identify potential interactors of TRPC5OS in tumor cells, and the interaction between TRPC5OS and interactors was validated by co-immunoprecipitation (CO-IP), western blots, and immunofluorescent staining. Glucose uptake was measured by liquid scintillation spectrometry. TRPC5OS highly expresses both in breast tumors and cell lines, and might be an independent prognostic marker for breast cancer patients. Overexpressed TRPC5OS promotes breast cancer cell proliferation, cell cycle progression, and enhances tumor xenograft growth. Mass spectral and CO-IP data showed that TRPC5OS interacts with ENO1. We also demonstrate that TRPC5OS could enhance ENO1/PI3K/Akt-mediated glucose uptake in breast cancer cells. Our study demonstrated that TRPC5OS promotes breast tumorigenesis by ENO1/PI3K/Akt-mediated glucose uptake. TRPC5OS might be an independent prognostic marker and potential therapeutic target for breast cancer patients.

Analytical Methods for the Determination of 90Sr and 239,240Pu in Environmental Samples.

Artificial long-lived radionuclides such as 90Sr and 239,240Pu have been long released into the environment by human nuclear activities, which have a profound impact on the ecological environment. It is of great significance to monitor the concentration of these radionuclides for environmental safety. This paper summarizes and critically discusses the separation and measurement methods for ultra-trace determination of 90Sr, 239Pu, and 240Pu in the environment. After selecting the measurement method, it is necessary to consider the decontamination of the interference from matrix elements and the key elements, and this involves the choice of the separation method. Measurement methods include both radiometric methods and non-radiometric methods. Radiometric methods, including alpha spectroscopy, liquid scintillation spectrometry, etc., are commonly used methods for measuring 239+240Pu and 90Sr. Mass spectrometry, as the representative of non-radiometric measurement methods, has been regarded as the most promising analytical method due to its high absolute sensitivity, low detection limit, and relatively short sample-analysis time. Through the comparison of various measurement methods, the future development trend of radionuclide measurement is prospected in this review. The fully automatic and rapid analysis method is a highlight. The new mass spectrometer with ultra-high sensitivity shows strong analytical capabilities for extremely low concentrations of 90Sr, 239Pu, and 240Pu, and it is expected to develop determination methods with higher sensitivity and lower detection limit.

Investigation of Sediment Records of Kulakçayiri Lake (Istanbul)

In this study, the date of the Holocene sediments of Kulakçayırı Lake was determined and the sedimentation rates were calculated. The determined sedimentation rates provide important clues about the climatic and ecological characteristics of the study area. Especially in aquatic environments, it is important to date sediment processes in order to monitor the time-dependent changes in the pollution processes of sediments. In this context, radiocarbon (14C) analysis was performed in order to date the sediments. Liquid scintillation spectrometry was used to find the radioactivity of the 14C isotope. Three drilling samples were taken from the study area (Kulakçayırı Lake / Istanbul) for 14C analysis. According to the results of 14C analysis of the samples taken; Sediment deposition in SK-1 sample took place in 5599 years, in SK-2 in 7596 years and in SK-3 in 8060 years. Sedimentation rates are; SK-1> SK-2> SK-3. From the data obtained, it was observed that the sedimentation rate has different rates at different points of the lake. There is no stream bringing material to the lake. Therefore, it can be said that a slow storage dominates the lake in general.

МЕТОДИЧЕСКИЕ ПОДХОДЫ К МОНИТОРИНГУ УГЛЕРОДА-14 ДЛЯ КОНТРОЛЯ ЕГО РАДИАЦИОННОГО ВОЗДЕЙСТВИЯ НА ПЕРСОНАЛ И НАСЕЛЕНИЕ

Purpose: Analysis of the current regulatory and methodological framework on control of doses from intake of 14C for the personnel and the public living in the control area of the nuclear power plant (NPP). Identifying the most informative methods of controlling radiation impact of 14C on a human being. Material and methods: Research literature on radiation impact of naturally occurring 14C; 14C entering the environment as a result of nuclear weapon tests; and 14C entering workplaces and the control area of NPP has been reviewed. Dose coefficients and other radiation characteristics of 14C provided in IAEA, ICRP and UNSCEAR publications have been summarized. Results: According to UNSCEAR, annual radiation burden caused by global 14C is the highest one (about 80 %) among radiation burdens associated with four critical naturally occurring cosmogenic radionuclides: 3H (0.01 µSv/year), 7Be (3.0 µSv/year), 14C (12 µSv/year) and 24Na (0.2µSv/year). The main way of 14C intake is the alimentary one when this isotope enters the human body with food. Dose from this kind of intake of global 14C can reach 40 µSv. The annual dose caused by aerogenic (inhalation) way of intake of global 14C does not exceed 1 µSv. The most informative methods of dose assessment for the personnel of NPP and the public living in the control area involve measurement of content of 14C in top soil, vegetation and food products. Conclusions: Significant amount of 14C enters the environment within the control area during operation of NPP, which causes the public radiation dose exceeding the dose from global 14C. The most informative objects characterizing content of technogenic 14C in the control area of NPP are top soil (humus) and vegetation. The liquid scintillation spectrometry involves sample preparation by burning of samples in oxygen with capturing of generated carbon dioxide and its transfer into organic solvent. This is the most technologically viable method for mass control of 14C content in samples of top soil and vegetation.

Distribution of tritium and its compounds in the environment under normal conditions of operating of Kalininskaya nuclear power plant

Tritium is one of the most important dose-forming radionuclides that determine the radiation situation in the area where nuclear fuel cycle enterprises are located. At the same time, it is not possible to catch the tritium formed during the operation of a nuclear power plant using modern, efficient and cheap technologies. This causes an increase in its concentration in environmental objects and an increase in the contribution of technogenic tritium to the radiation load of the population. Therefore, the task of monitoring the formation of tritium during the operation of nuclear power plants, the content of tritium in emissions and discharges of nuclear power plants, as well as the distribution of this radionuclide in the environment is especially urgent today. The study aims to analyze the environmental pollution due to emissions and discharges of tritium from the Kalininskaya nuclear power plant, the process of spreading tritium by air, as well as the accumulation of this radionuclide in water bodies, soil and food products grown in the area of the nuclear power plant. The following methods, developed by the specialists of the Burnasyan Federal Medical Biophysical Center were used during the research: 1) "Method for determining the volumetric activity of organic and inorganic tritium compounds in water bodies by liquid scintillation spectrometry". 2) "Methodology for determining the concentration of organic and inorganic tritium compounds in the air of the environment and industrial premises". 3) "The method for determining the specific activity of tritium compounds in soil and vegetation" was developed and tested in the course of field studies at the Kalinin NPP. As a sample preparation we used the method based on burning a selected sample in a specialized Pyrolyser-6 Trio oven. All prepared counting samples were measured by liquid scintillation spectrometry on a counter Tri-Carb 3180TR/SL. On the basis of an integrated approach to assessing the content of tritium and its compounds in air, water, soil and food, an analysis of the formation of environmental pollution due to emissions and discharges of tritium from the Kalinin NPP was carried out. It is shown that the transport of emissions from the NPP by air and the wind direction prevailing in the territory of the NPP location have a significant importance in the formation of the contribution to the ingress of tritium into foodstuffs. The necessity of taking into account the ingress of tritium and its compounds with nuclear plant emissions into the environment in the task of optimization of radiation protection of the population under conditions of normal operation of NPP is shown.