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Data of destructive radiochemical analysis of the isotopic composition, mass content and, burnups of 12 nuclear fuel samples irradiated in a VVER-440 reactor are reported. The experimental data obtained were analyzed to determine the correlation dependences of the mass content of nuclides on the depth of fuel burnup. A comparative analysis of the results obtained with the data of other researchers has been performed.

O rio Tietê drena uma área composta por seis sub-bacias, com extensão de 1100 km e é considerado economicamente um dos rios mais importantes do Brasil. Enormes quantidades de efluentes industriais contaminados e esgoto foram despejados neste rio ao longo dos anos, a ponto de ser considerado um dos rios mais poluídos do mundo. Considerando-se a grande extensão do rio Tietê, suas características litológicas, a ocupação do solo e a utilização de seus recursos hídricos, o rio foi dividido em três regiões denominadas \"Alto Tietê\", \"Médio Tietê\" e \"Baixo Tietê\". Este estudo faz parte do projeto intitulado \"Avaliação da poluição por metais e oligoelementos em sedimentos fluviais - estudo de caso do Rio Tietê, Estado de São Paulo\", que teve como objetivo determinar a concentração e distribuição de elementos maiores e traços, em particular metais, que apresentam altos níveis de toxicidade em sedimentos superficiais do rio Tietê, desde a sua nascente até a foz. Como estudo complementar, esta dissertação tem como objetivo determinar os teores dos radionuclídeos naturais (238U, 226Ra, 210Pb, 232Th, 228Ra e 40K) e artificial (137Cs) nos sedimentos ao longo de toda a extensão do rio Tietê; metais pesados (Cd, Cr, Cu, Ni, Pb e Zn) e alguns elementos traços (As, Co, Hf e Sc) nos sedimentos coletados na região do \"Baixo Tietê\", visando avaliar a linha de base desses elementos e a extensão da contaminação. Para alcançar esses objetivos, os elementos de interesse foram analisados utilizando-se as técnicas apropriadas para a determinação de cada elemento. A determinação de Cu foi realizada utilizando-se a técnica de espectroscopia de emissão atômica com plasma indutivamente acoplado; a determinação dos metais Cd, Ni e Pb foi realizada utilizando-se a técnica de espectrometria de absorção atômica com forno de grafite; a determinação de As, Co, Cr, Hf, Sc, U, Th e Zn foi realizada por análise por ativação com nêutrons instrumental; a determinação dos radionuclídeos 226Ra, 228Ra, 210Pb, 40K e 137Cs foi feita utilizando-se a técnica de espectrometria gama de alta resolução. Para avaliar a qualidade dos sedimentos e seu grau de poluição foram utilizadas as ferramentas Fator de Enriquecimento e Índice de Geoacumulação. Os resultados de Fator de Enriquecimento obtidos para os elementos As, Cd, Cr, Cu, Ni, Pb e Zn, utilizando-se como referência os valores médios da crosta, indicam que a região do \"Alto Tietê\" e do \"Médio Tietê\" apresentam influência antrópica, sendo que o maior impacto ocorreu para os elementos Cd, Cu e Zn e em escala menor o Ni. Os resultados do Índice de Geoacumulação obtidos para Cd, Cr, Cu, Ni e Zn, utilizando como referência os valores de concentração da região, indicaram que a região do Alto Tietê está poluída, seguida da região do Médio Tietê e a região do Baixo Tietê não apresenta indícios de contaminação. Os resultados obtidos para As e Pb mostraram que houve uma melhora na qualidade dos sedimentos, nos últimos 12 anos e que esses elementos apresentam uma linha de base superior aos valores médios da crosta terrestre. The Tietê River drains an area composed by six sub-basins, with an extension of 1,100 km and is considered economically one of the most important rivers in Brazil. Huge amounts of contaminated industrial effluents and sewage have been dumped into this river over the years, to such an extent that it was considered one of the most polluted rivers in the world. Considering the great extension of the Tietê River, its lithological characteristics, the occupation of the soil and the use of its water resources, the river was divided into three regions called High Tietê River, Middle Tietê River and Low Tietê River. This study is part of a project entitled \"Evaluation of pollution by metals and trace elements in river sediments - case study of Tietê River, State of São Paulo, Brazil\", which aimed at determining the concentration and distribution of major and trace elements in particular metals, which present high levels of toxicity, in sediments of the Tietê River, from its source to its mouth. As a complementary study, this dissertation aims at determining the levels of natural (238U, 226Ra, 210Pb, 232Th, 228Ra and 40K) and artificial (137Cs) radionuclides in the sediments along the entire length of the Tietê River; heavy metals (Cd, Cr, Cu, Ni, Pb and Zn) and some trace elements (As, Co, Hf and Sc) in the sediments collected in the \"Low Tietê River\" region, in order to analyze the baseline of these elements and the extent of contamination. To fulfill these objectives, the elements of interest were analyzed using the appropriate techniques. For the determination of Cu, the technique used was inductively coupled plasma optical emission spectrometry; the elements Cd, Ni and Pb were determined by graphite-furnace atomic absorption spectrometry; As, Co, Cr, Hf, Sc, U, Th and Zn were determined by using instrumental neutron activation analysis; the activity concentration of radionuclides 226Ra, 228Ra, 210Pb, 40K and 137Cs was determined by using high resolution gamma ray spectrometry. To evaluate the quality of the sediments and their degree of pollution, the Enrichment Factor and Geoaccumulation Index tools were used. The Enrichment Factor results obtained for the elements As, Cd, Cr, Cu, Ni, Pb and Zn, using as reference the mean values of the crust, indicate that the region of High Tietê River and Middle Tietê River have anthropogenic influence, with the biggest impact occurring for the elements Cd, Cu and Zn and, on a smaller scale, Ni. The results of the Geoaccumulation Index obtained for Cd, Cr, Cu, Ni and Zn, using as reference the concentration values of the region, indicated that the High Tietê River region is polluted, followed by the Middle Tietê River region and the Low Tietê River region does not present evidence of contamination. The results obtained for As and Pb showed that there was an improvement in the quality of the sediments, in the last 12 years, and that these elements present a baseline above the mean values of the crust.

Current methods for quantitative dissolution of solid PuO2 involve lengthy dissolution times. The adaptation of mediated electrochemical oxidation, which uses an electrochemically produced oxidizing agent to catalyze dissolution, has been explored for radiochemical analysis scale dissolutions of PuO2. The effects of temperature, electrode material, and electrocatalyst on the dissolution kinetics were explored. Under conditions examined in this study, complete dissolution of tens of milligrams of solid PuO2 can be achieved in less than 1 h at ambient temperature. This methodology could be adapted to dissolve other metal oxides.

An article contents the review of the data on the content of polonium and lead content: 210Po, 210Pb in natural entities, obtained from literary sources. The review is given of the existing methods for 210Po and 210Pb content investigation in different entities as well as the analysis of the expedience of the applying of the given polonium and lead content investigation in the foodstuffs technique for the use in a method under development of the radiochemical laboratory of the Institute. More perfect and simple for realization than existing method is given for 210Po and 210Pb content investigation in the foodstuffs from a sample with not more than 1.0 kg weight with minimal detectable activity not more than 0.01 Bq. The results are given of the investigation of 210Po and 210Pb content in the certain types of the foodstuffs sampled in the kitchen gardens located in Leningrad region and bought in the trade network of Saint-Petersburg. Estimation of potential average annual population internal exposure dose (Eint) is carried out due to 210Po and 210Pb content in the investigated foodstuffs which are consumed by the local population. For the estimation of the internal exposure doses we used the data on the food rations of adult population of the settlement of the city type according to the data of Rosstat and Internet-resources. It is demonstrated that population internal exposure dose even from several natural radionuclides taking into account consumption of a limited set of foodstuffs could exceed the exposure dose from artificial radionuclide in tens times even for the territories radioactively contaminated after the Chernobyl NPP accident.

An article contents the review of the data on the content of polonium and lead content: 210Po, 210Pb in natural entities, obtained from literary sources. The review is given of the existing methods for 210Po and 210Pb content investigation in different entities as well as the analysis of the expedience of the applying of the given polonium and lead content investigation in the foodstuffs technique for the use in a method under development of the radiochemical laboratory of the Institute. More perfect and simple for realization than existing method is given for 210Po and 210Pb content investigation in the foodstuffs from a sample with not more than 1.0 kg weight with minimal detectable activity not more than 0.01 Bq. The results are given of the investigation of 210Po and 210Pb content in the certain types of the foodstuffs sampled in the kitchen gardens located in Leningrad region and bought in the trade network of Saint-Petersburg. Estimation of potential average annual population internal exposure dose (Eint) is carried out due to 210Po and 210Pb content in the investigated foodstuffs which are consumed by the local population. For the estimation of the internal exposure doses we used the data on the food rations of adult population of the settlement of the city type according to the data of Rosstat and Internet-resources. It is demonstrated that population internal exposure dose even from several natural radionuclides taking into account consumption of a limited set of foodstuffs could exceed the exposure dose from artificial radionuclide in tens times even for the territories radioactively contaminated after the Chernobyl NPP accident.

Development of 3H, 14C, 41Ca, 55Fe and 63Ni radiochemical analysis methods were carried out independently by two laboratories using both inactivate and activated concrete samples. Two preliminary radioanalytical procedures for the non-volatile radionuclides (41Ca, 55Fe, 63Ni) and one Thermal oxidation method for the volatile radionuclides (3H, 14C) were developed. The difficulties in the method development and analysis of results are discussed.

Determination of long-lived radionuclides is critical for environmental radioactivity investigation, environmental processes studies and decommissioning of nuclear facilities. This paper summarizes main progress in the radiochemical analysis in our laboratories in the past years for determination of ultra-low level radionuclides in the environment using chemical separation combined with mass spectrometry measurement. The analytical methods for determination of ultra-low level 129I and its chemical species in various environmental samples are highlighted. The methods developed in our laboratories for characterization of decommissioning waste, especially the methods for the determination of difficult-to-measure radionuclides using sequentially chemical separation and radiometric measurement are also briefly presented. This is also a part of the Hevesy Medal award lecture in the RANC2019 conference.

General approaches to the automation of chemical analysis and radiochemical control in nuclear power engineering are discussed. For radioactive media with the highest specific activity, the necessity of the automation of the off-line control mode for minimizing the amount of the formed radioactive wastes is proved. Possibilities of the automation of the off-line analysis of primary coolants of nuclear power installations in the determination of chloride and sulfate ions are considered as an illustration. Based on a comparison with the results of analysis by ion chromatography, it is shown that the developed methods possess comparable analytical characteristics. A procedure for the determination of uranium using principles of cyclic injection analysis ensuring lower limits of detection in comparison with radiometric procedures is presented to illustrate possibilities of radiochemical analysis. The thesis about the advisability of transition to flow methods of analysis instead of batch methods used nowadays is substantiated.

The aim of this paper is to describe the implementation of the REVIRA program in Spain, with a description of the elements that have to be determined within this. Radiochemical analyses are increasingly demanded in routine laboratories for monitoring radionuclides from environmental samples, nuclear power plants, water treatment plants, nuclear medicine and industrial uses, among others. Thus, benefits of automation are of great interest in the radiochemical field. In this contribution, different strategies used for automating radiochemical analyses are discussed, encompassing fully and partially automated flow methodologies. Thus, automated analytical protocols of extraction and preconcentration of radionuclides are presented, together with their coupling to radiometric detectors or inductively coupled plasma mass spectrometers (ICP-MS). A detailed description about the determination of the most interesting isotopes with flow techniques, such as Ra, U, Th, Sr, Y, and Tc is provided.

Novel methods for sample preparation by adapting an automated chromatography system to radiochemical analysis for analysis of trace impurities is reported. The methods were optimised with sample to sample times of 15–35 min. These samples were used to analyse 75 trace elements in uranium and plutonium and for the quantification of trace actinides. Uranium and plutonium samples were analysed with less than 4–7% relative standard deviation. The results were comparable with current methods for analysis and offer additional safety and efficiency benefits. The methods yielded a 20-fold reduction in sample size and a fourfold reduction in waste produced.

We address the problem of evaluating measurements of radionuclide activity concentration from a robust Bayesian perspective. As shown in previous studies, Bayesian incorporation of available prior information on the activity levels, together with the measured values, leads in general to an improvement in the quality of radioanalytical results. Since the specific form of the employed prior is a critical aspect of the Bayesian framework, in the present paper we distort the prior distribution in order to evaluate how it influences the final activity estimate. We applied this procedure to inter-laboratory proficiency test data obtained by the laboratories that perform radiochemical analysis for the Spanish radioactive monitoring network. We found that in the present application the Bayesian methodology is indeed robust, as modifying the specific form of the prior has little effect on the activity estimate. Similar sensitivity analysis could be applied to the Bayesian evaluation of measurements of other quantities for which prior knowledge is available.

This paper reports the results obtained in a Nordic Nuclear Safety Research project during the second intercomparison exercise for the determination of difficult to measure radionuclides in decommissioning waste. Eight laboratories participated by carrying out radiochemical analysis of 3H, 14C, 36Cl, 41Ca, 55Fe and 63Ni in an activated concrete. In addition, gamma emitters, namely 152Eu and 60Co, were analysed. The assigned values were derived from the submitted results according to ISO 13,528 standard and the performance assessments were determined using z scores. The measured results were compared with activation calculation result showing varying degree of comparability.

Contaminated wounds are a common route of internal deposition of radionuclides for nuclear and radiation workers. They may result in significant doses to radiosensitive organs and tissues in an exposed individual’s body. The United States Transuranium and Uranium Registries’ whole-body donor (Case 0303) accidentally punctured his finger on equipment contaminated with plutonium nitrate. The wound was surgically excised and medically treated with intravenous injections of Ca-DTPA. A total of 16 g Ca-DTPA was administered in 18 treatments during the 2 months following the accident. Ninety-three urine samples were collected and analysed over 14 years following the accident. An estimated 239Pu activity of 73.7 Bq was excreted during Ca-DTPA treatment. Post-mortem radiochemical analysis of autopsy tissues indicated that 40 years post-accident 21.6 ± 0.2 Bq of 239Pu was retained in the skeleton, 12.2 ± 0.3 Bq in the liver, and 3.7 ± 0.1 Bq in other soft tissues; 1.35 ± 0.02 Bq of 239Pu was measured in tissue samples from the wound site. To estimate the plutonium intake, late urine measurements, which were unaffected by chelation, and post-mortem radiochemical analysis results were evaluated using the IMBA Professional Plus software. The application of the National Council on Radiation Protection and Measurements wound model with an assumption of intake material as a predominantly strongly retained soluble plutonium compound with a small insoluble fraction adequately described the data (p = 0.46). The effective intake was estimated to be 50.2 Bq of plutonium nitrate and 1.5 Bq of the fragment. The prompt medical intervention with contaminated tissue excision and subsequent Ca-DTPA decorporation therapy reduced 239Pu activity available for uptake and long-term retention in this individual’s systemic organs by a factor of 38.

The analytical method of Gd determination was developed with the aim to analyse Gd-148 in environmental and bioassay samples. It involves the use of anion exchange resin, extraction chromatography, and cation exchange resin. Alkaline fusion and calcium oxalate co-precipitation are used for solid samples dissolution and liquid samples preconcentration, respectively. Total method recovery was tested with natural Gd (Gd-157) using ICP-QQQ-MS. A maximum total recovery of 75 % was obtained.

191 p. En esta Tesis se desarrolla e implementa un procedimiento para la determinación conjunta de Fe-55 y Ni-63 en muestras medioambientales.También se desarrolla y propone un procedimiento general de validación para procedimientos radioanalíticos que posteriormente se aplicarán al procedimiento desarrollado permitiendo así su perceptiva validación previa a considerar como un método de rutina en el laboratorio.

The study of sub-barrier fusion is important to understand the dynamics of reactions involving weakly bound exotic nuclei. In most cases cross sections well below ≈ 1 mb need to be determined, but the limited beam intensity and background poses a great experimental challenge to measure it accurately. To overcome these problems we discuss a novel technique based on the use of radiochemical analysis. The advantages and limitations of this method are compared with the direct α -counting technique using the reaction 208Pb( 7 Li, 210Po) at E l a b = 39.3 MeV. The experiments were carried out at the BARC-TIFR Pelletron-Linac accelerator facility in Mumbai, India, and the radiochemical analysis at the University of Huelva, Spain.

Introduction The radiochemical purity (RCP) of technetium-99m labelled radiopharmaceuticals (RP) is important to ensure optimal scintigraphic image quality. In low-income settings, it may not be possible to use compendial analytical methods or expensive equipment for radiochemical purity analysis. All radiochemical analysis methods should however be validated against compendial or otherwise proven methods. To ensure the efficacy of RP prepared at Yaoundé General Hospital (YGH) Cameroon, this study cross-validated a cost-effective routine chromatographic method using a simple survey meter technique. A GMP-compliant method used at the University Medical Center Groningen (UMCG), the Netherlands was used as the comparator. Methods Sestamibi, HMDP and DMSA kits currently used at YGH were reconstituted at UMCG with about 2000 MBq of freshly eluted sodium pertechnetate as described by the manufacturer, and spiked with eluate of the same generator to obtain a range of impurity concentrations. Samples of technetium-99m RP were spotted on 1 × 10 cm iTLC-SG strips and developed in appropriate mobile phases. Each strip was first scanned on the chromatogram-scanner used at the UMCG (standard method), and immediately thereafter the strip was cut in two pieces and radioactivity from each portion was counted with a small survey meter from YGH. The percentage RCP for each TLC strip was calculated using both counting methods. Internationally recommended validation parameters and acceptance criteria were used. Student’s paired t-test or ANOVA were used with ‘no significant difference’ designated at a 95% confidence-interval (P ≥ 0.05). Linearity of the survey meter was determined for Tc-99m. Readings obtained with the survey meter were also plotted against the scanner results. Results and discussion The proposed method proved to be accurate (CV of mean RCP r2 ≥ 0.99) within the RCP range of approximately 80% to 100%, and robust (P > 0.05). LOD and LOQ were determined for the survey meter. Specificity depends on chemical separation. As we were validating the suitability of a method to quantify radioactivity, specificity was not included in the validation parameters. Conclusion The proposed method compared well with the standard method and is suitable as a reliable low cost method for limited resource settings.

Dedication: The research of the US Transuranium and Uranium Registries relies heavily upon postmortem autopsy findings and radiochemical analysis of tissues. The enormous debt owed to those now-deceased registrants who unselfishly voluntarily participated in the US Transuranium and Uranium Registries program through postmortem donation of their tissues and to those still-living registrants who have volunteered to be future postmortem tissue donors is hereby acknowledged with gratitude. The scientific findings derived from postmortem analysis of these tissues have been instrumental in advancing our understanding of the actinide elements in humans and have led to refinement, validation, and confidence in safety standards for those who work with these elements as well as for the general public. To these generous and anonymous persons who made this ultimate contribution, this paper is dedicated with great thanks and admiration.

Objective of the study: To conduct a comprehensive analysis and assessment of the dynamics of internal exposure levels in the territories contaminated due to the activities of the Mayak Production Association, based upon the results of long-term monitoring of the long-lived anthropogenic radionuclide body burden in residents of the Urals region. Materials and methods: The data of postmortem and in vivo examinations for three groups of population were analyzed: 1) residents of riverside villages of the upper and middle reaches of the Techa River, contaminated in 1949-1956 with liquid radioactive waste; 2) people who were exposed as a result of the 1957 accident on the territory of the East Urals Radioactive Trace; 3) residents of the Ozyorsk city, located at an 8 km distance from the enterprise. The following methods of the examinations were used: 1) radiochemical analysis of specimens of organs and tissues sampled at autopsy; 2) in vivo measurements with the use of the whole body counters. The results of measurements of cesium-137, strontium-90 and trans-uranium radionuclide body burden over the period 1950s – present are provided. Data analysis made it possible to distinguish two historically formed groups of population with the maximum levels of current strontium-90 and plutonium body burden. The first group included people who lived in the early 1950’s in the basin of the Techa River, for whom the levels of oral intake of 90Sr reached 1.4 MBq/year. The second group comprised residents of the Ozyorsk city, for whom the levels of inhalation intake of plutonium in the period 1951–1958 reached 8 Bq/year. Conclusion: Estimates of the committed effective doses due to the intake of long-lived radionuclides over the period from 1949 through 2012 for critical groups of residents of the Urals were: 300 mSv for former residents of the Muslyumovo settlement on the Techa River (90Sr contribution – 85%) and 13 mSv for residents of the Ozyorsk city (the contribution of trans-uranium radionuclides is 30%).

The aim of the study was to obtain 234U and 238U specific activity in the water of groundwater supplies of Leningrad region and St-Petersburg and to estimate the possibility of their using from the point of view of radiation and chemical toxicity of the main dose-forming uranium isotopes usually containing in the underground waters. The study was focused on the water of functioning and exploratory groundwater supplies concerning the safety of water consumption taken into account radiation and chemical index. Data on the levels of natural uranium isotopes specific activity in the sources under investigation was obtained using radiochemical analysis with the subsequent alpha-spectrometric measurement of the counting samples. 58 samples of natural groundwater were analyzed during the period from February of 2011 till the May of 2017. The volume of the native water samples was from 10 l to 30 l, measuring time for each counting sample was 6 – 12 hours, which allowed measuring the radionuclides specific activity value at the level of 0.0002 Bq/kg. The values of 238U specific activity varied within 0.0002 Bq/kg – 0.06 Bq/kg, the average value was 0.007 Bq/kg. The values of 234U specific activity varied within 0.0006 Bq/kg – 0.111 Bq/kg, the average value was 0.013 Bq/kg. The average value of the specific activities ratio 234U/238U was 2.12 and the range of this value was 1.00 – 8.00. The results of carried out investigations demonstrates that the specific activity values of uranium isotopes could differ more then by an order of magnitude even in the borders of same aquifer of a small settlement. 238U specific activity value does not exceed 0.02 Bq/kg and 234U specific activity value does not exceed 0.04 Bq/kg for the vast majority of analyzed sample. The value of the ratio 234U/238U was 1.00 – 4.00 for 98.3% of analyzed sample. It is possible to conclude with a high probability that the water from the groundwater supplies of Leningrad region and St-Petersburg is safe for consumption by population concerning 234U and 238U content as from the point of view of radiological factor, so from the point of view of chemical toxicity.

Protactinium-233 (233Pa) is used as a tracer for radiochemical analysis and is of particular interest as an isotope dilution mass spectrometry (IDMS) spike for 231Pa/235U radio-chronometry. To this end, we present massic activity determinations by two methods for a 233Pa solution, which was prepared at Lawrence Livermore National Laboratory (LLNL) and is being characterized at multiple labs as part of a 231Pa reference material production project. One activity determination method was 4πβ-γ anti-coincidence counting in a multi-dimensional extrapolation model, with Monte Carlo corrections. An independent massic activity determination was completed by $$\gamma$$ -ray spectrometry using 5 high purity germanium (HPGe) detectors using 5 $$\gamma$$ -ray lines. The anti-coincidence and $$\gamma$$ -ray spectrometry results agree and have combined standard uncertainties of about 0.33% and 1.0% respectively. In addition, the two methods were combined to derive $$\gamma$$ -ray emission probabilities from 233Pa decay.

The aim of the study was to estimate the radiation characteristics of the mineral natural drinking table and medical-table water, consumed by the population of St-Petersburg and Leningrad region. This study was focused on the bottled natural mineral drinking water, available in St-Petersburg and Leningrad region market, as well as on the natural mineral drinking water sampled from the St-Petersburg groundwater supplies. Data on the levels of radionuclides specific activities in the sources under investigation was obtained using radiochemical analysis with the subsequent radiometric or spectrometric measurement of the counting samples. 107 samples of mineral natural drinking water were analyzed during the period from1999 till the December of 2017. Assessment included estimation in different combinations of the levels of gross alpha- and beta activities, specific activities of226Ra,224Ra,228Ra,210Pb,210Po,238U,234U,40K and222Rn, as well as the estimation of the index of conformance of the water to the requirements of the radiation safety. The mentioned index is the sum of the ratios of the specific activities of the individual radionuclides to the corresponding guidance levels. Exceedance of the index of conformance for the gross alpha-activity was detected for 87% of analyzed water samples; for the gross beta-activity – for 18% of the samples. Exceedance of the index of conformance of the water to the requirements of the radiation safety was detected for 40% of the analyzed samples. Exceeding of the guidance level of radionuclide in drinking water was found: in 24% water samples for226Ra concentration, in 24% – for228Ra concentration, in 3,5% – for224Ra concentration. An exceedance of the guidance levels for210Pb,210Po,238U,234U, 40K and222Rn in analyzed samples was not detected. The main contribution to the sum of the ratios of the specific activities of the natural radionuclides to the corresponding guidance levels and, correspondently to the exposure dose to the population of St-Petersburg and Leningrad region from the consumption of the mineral drinking water give226Ra,228Ra and222Rn the total contribution of which to the mentioned value exceeds 90%.

Mineral natural table, medical-table and medical water is usually characterized by enhanced mineralization, so annual consumption of such water for drinking and cooking is much lower than standard water consumption of adult population. The limitation of population exposure due to mineral natural table and medical-table water could be achieved by the implementation of limitation of their consumption. The aim of the investigation is to estimate potentially possible population exposure doses from mineral natural medical water consumption on an example of the water which is used for drinking therapy in the complex of sanatorium health resort treatment of patients in one of the sanatoriums of Saint-Petersburg. The data on mineral medical water radionuclides specific activity values used for patients exposure doses estimation was obtained during implemented radiochemical analysis carried out using the techniques developed in the Institute of Radiation Hygiene. Obtained results of the investigations and their analysis demonstrated that potentially possible patients’ maximal annual effective exposure doses due to implementation of mineral natural medical water for drinking therapy in the complex of sanatorium health resort treatment will not exceed definitely the reference dose level, recommended by WHO, equal to 0.1 mSv/year because of a low amount of water consumption prescribed by a physician. It is clear unreasonable to set limitations on natural radionuclides content in mineral medical water because patients take it as a medicine according to physician prescribing and the consumption of such water is connected with their therapy properties. Principle of justification of the procedures appointment has to be applied when the course of mineral medical water treatment is prescribed. The essence of the principle is to compare therapy (medical) benefits as a result of treatment with the damage to health as a result of radiation exposure. It is necessary to estimate the effective internal exposure doses due to mineral natural medical water consumption for different age groups of population for the process of justification of therapy procedures.

The radioactivity concentration of 210Po, 226Ra, and U in Cauvery river basin was analyzed using radiochemical analysis, emanometry, and LED fluorimetry, respectively. Due to transfer with water in cracks and pores, leaching, and heavy usage of phosphate fertilizers, 210Po, 226Ra, and U radionuclides get into the environmental samples studied. The 210Po concentration ranges from 0.7 ± 0.11 to 5.0 ± 0.7 and from 0.83 ± 0.12 to 5.2 ± 0.8 mBq L–1; the 226Ra concentration, from 11.7 ± 1.8 to 62 ± 9 and from 10.5 ± 1.6 to 68 ± 10 mBq L–1; and the U concentration, from 0.08 ± 0.01 to 4.4 ± 0.7 and from 2.0 ± 0.3 to 7.4 ± 1.1 ppb in river and borewell water samples, respectively.

Quantification of several alpha and beta emitters in mixtures of radionuclides arouses great interest in many fields such as surveillance around nuclear power plants, radioecology, accidental situations or drinking water control. Radiochemical separations are commonly used to deal with this issue. However, deconvolution methods for the analysis of LS spectra have been developed to avoid time-consuming radiochemical separations. The deconvolution procedure usually consists of the comparison of the spectrum that has to be analysed with a set of standard spectra. In order to obtain reliable results, the library of spectra used in the deconvolutions must fit with the analysed sample. For this reason, in order to determine all radionuclides included in the drinking water directive it has been established a strategy to select the radionuclides whose LS spectra must be included in the Partial least squares (PLS) model.

Radioactive waste generated in decommissioning activities need be classified according to their radioactive content. The radiological information required by national authorities includes diverse alpha and beta emitters, which can only be determined after a radiochemical separation process. This paper presents the work on the development of radiochemical methods for the simultaneous separation of several radionuclides in concrete, steel and graphite samples, on the basis of individual sample treatments which merge in a common radiochemical separation procedure based on extraction chromatography.

We report a study of a fast radiochemical method to determine the activity of 131I via the radiochemical recovery obtained with a 129I tracer. Previous methods were valid for low levels of 131I activities. In the new method, we developed a correction using the 29.7-keV X-ray peak from Xe, taking into consideration that this peak originates from both and 131I decay. This enables quantitation of high levels of 131I activity. Furthermore, for a very high 131I activity, one can use the 39.6-keV gamma peak which is unique to 129I. Combining both approaches enables quantitation of 131I activities up to 200 times that of the 129I recovery tracer.

A LabVIEW®-based software for the control of the fully automated multi-sequential flow injection analysis Lab-on-Valve (MSFIA-LOV) platform AutoRAD performing radiochemical analysis is described. The analytical platform interfaces an Arduino®-based device triggering multiple detectors providing a flexible and fit for purpose choice of detection systems. The different analytical devices are interfaced to the PC running LabVIEW®VI software using USB and RS232 interfaces, both for sending commands and receiving confirmation or error responses. The AUTORAD platform has been successfully applied for the chemical separation and determination of Sr, an important fission product pertinent to nuclear waste.

The activity concentrations of naturally occurring radionuclides (such as 226Ra, 210Pb and 210Po) and long lived 137Cs were measured in a total of 119 tissue samples (43 blubber, 43 liver, and 33 muscle samples) from 40 ringed seals and 4 bearded seals collected in the Arviat area of Canada during the fall of 2014. Activity concentration of 210Po was measured in all seal liver and muscle samples individually. The average 210Po activity concentrations were 25 ± 7.6 Bq/kg fresh weight (fw) in muscle and 211 ± 58 Bq/kg fw in liver for ringed seals, and 20 ± 6.1 Bq/kg fw in muscle and 231 ± 150 Bq/kg fw in liver for bearded seals. Due to insufficient sample material for most samples collected, gamma counting for radioactive caesium and radiochemical analysis for 226Ra and 210Pb were performed for pooled samples. Activity concentrations of 210Pb and 226Ra were generally below detection limits. While 134Cs activity concentration was not detectable, 137Cs activity concentration was detected in muscle and liver samples. On average, the 137Cs activity concentrations were 0.25 ± 0.05 and 0.12 ± 0.04 Bq/kg fw in muscle and liver samples of ringed seals, and 0.11 ± 0.02 and 0.10 ± 0.03 Bq/kg fw in muscle and liver samples of bearded seals, respectively. Neither 210Po nor 137Cs were detected in the blubber samples. This study confirmed that 210Po is the dominant contributor to radiation doses resulting from seal consumption. Man-made contaminant 137Cs only contributes less than 0.01% of the total ingestion dose obtained from Arviat seals.

The accuracy and precision of a radiotracer’s activity concentration is essential in obtaining credible and sustainable analytical data. This study illustrated the in-house re-calibration method of an unknown Plutonium-236 (236Pu) solution by radiochemical analysis and alpha spectrometry that have been completed in our laboratory. The objective of this study was to recalibrate and determine the accurate activity of the unknown radioactive solution, which was a challenging task for five years experienced radiation measurement laboratory (RML). Six non-sustained consecutive test points data were below 3σ in the weekly quality control chart of 236Pu blank samples. The cause and effect tool was implemented to investigate the discrepancy in data by evaluating several parameters. The tracer was the most probable parameter that needed to be verified due to some uncontrolled laboratory and vial storage conditions. It was assumed that radioactive hot particles could be formed, producing a concentric fraction of Plutonium in the unknown 236Pu solution. Therefore, the recalibration of the unknown 236Pu activity concentration solution was proposed and implemented. To confirm this observation, triple blank samples underwent a radiochemical analysis, and they were found to be less than the certified value. The verified recalibration method was approached through a full radiochemical pre-preparation (triple full digestions, triple purifications). Then, a certified Plutonium-242 reference (242Pu) was used as across calibration source, and measurements were done using spectrometry measurements. The average of the recalibrated values and the associated uncertainties were estimated to be 0.632 ±0.024 in the 236Pu solution. The new verified concentration value was validated with the analysis of two different International Atomic Energy Agency (IAEA) Certified Reference Materials (CRMs), and the obtained results were found to be in good agreement with the IAEA certified values. Therefore, the method used to recalibrate the activity concentration was successful and it can be implemented for recalibrating unknown activity sources in the future. The newly derived 236Pu activity concentration can be used as a verified radiotracer for future plutonium radioisotopes analytical applications. Conclusively, professional and decent practice of radio analytical laboratories should be conducted following quality management systems.

Characterisation of FiR1 TRIGA Mark II research reactor in Finland relies on a combination of modelling and experimental results. Modelling is used in order to form an estimation of material specific activation levels. This information is used, for example, in planning of the dismantling process and waste management. Since some uncertainties are present in modelling results, experimental verification of activity levels are needed. Non-destructive analysis (NDA) using gamma spectrometry can be carried out for gamma emitting radionuclides, whereas analysis of alpha and beta emitting radionuclides, termed also difficult to measure (DTM) radionuclides, requires chemical separations and purification of the radionuclide of interest. Due to the lengthy and costly radiochemical analysis of DTM, a scaling factor is often determined to link the gamma emitting radionuclides with DTM. For FiR1, scaling factors are determined prior to the active dismantling phase and thus activity and nuclide vector calculations of waste packages can be carried out during, or even after, the active dismantling phase.

The application of organic resins in radiochemical practice is limited by virtue of their limited stability under various conditions. A very large number of scales of insoluble metal oxides and hydrous oxides possess ion-exchange and other important properties which make them very useful for the various separation processes or analytical determinations. The hydrous oxides of multivalent metals, such as Nb, Ta, Sb, Mo, and W, have cation-exchange properties. The good resistance of inorganic ion exchangers against radiation effect and heat means that they are very effective as semipermeable membranes. Some gas chromatographic separations have been performed successfully on well-defined crystalline inorganic ion exchangers, such as zirconium phosphate and zirconium arsenate. Lykourghiotis and co-workers have reported that rapid determinations can be achieved with selective retention of some organic compounds on an hydrated antimony pentoxide column.

Exposure doses estimations from plutonium isotopes are given for population living on the territories of Bryansk region contaminated after the Chernobyl accident. For calculations model representations of the plutonium migration in the system soil-man are used. Effective dose from inhalation intake of resuspended activity for population and agricultural machine operators (critical group) is investigated. It is shown that expected annual effective dose due to dust lifting from the contaminated ground surface doesn't exceed 5 µSv for population and 30 µSv for agricultural machine operators (for 1992). Exposure doses were additionally estimated basing on autopsy material radiochemical analysis, which permitted to obtain plutonium isotopes concentration in the organs and tissues of inhabitants of contaminated territories. It was established that annual effective dose from plutonium acquired in 1986-1992 is about 25 µSv.

Naturally occurring radionuclide 210Po which is an element of 238U decay series, contribute to the radiation that normally people are exposed. Drinking water samples collected from Cauvery river basin of south interior Karnataka State, India were analysed for the activity of 210Po using radiochemical analysis technique. The estimated concentration of 210Po in river water ranges from 0.86 to 4.49 mBq l−1, and its mean value is 2.67 ± 1.09 mBq l−1. The concentration of 210Po in bore well water ranges from 1.89 to 4.18 mBq l−1 and its mean value is 3.22 ± 0.67 mBq l−1. The dissolved radium concentration in river water varies from 9.09 mBq l−1 to 55.07 mBq l−1 with an average of 32.33 ± 14.16 mBq l−1. Total ingestion dose rate due to 226Ra and 210Po varies from 2.61 to 15.00 μSv y−1 with a mean value of 8.95 ± 3.74 μSv y−1, which is less than the recommended value by ICRP (International commission on radiological protection).

A reliable determination of natural and anthropogenic radionuclides in environmental samples is necessary to comply with the radiation protection and environmental regulations. This paper presents the results of the characterisation of massic activities of natural and anthropogenic radionuclides in soil and water matrices produced as test items to conduct the proficiency test ERAD-PT-2013. The proficiency test ERAD-PT-2013 was designed to investigate analytical performance in analysing both natural and anthropogenic radionuclides, to assist laboratories to identify analytical problems, and to improve the quality of measurement results. The proficiency test items, their spectral interferences and the activity concentration levels of the analytes were designed in a way to enable identification of potential analytical problems. Methodologies, data evaluation approach and evaluation of proficiency test results for each radionuclide are described and discussed.

Data on natural radionuclides content in drinking-water of North-Eastern area of Russian Federation obtained in long-term investigations is presented; population internal exposure doses estimation from the drinking-water consumption is carried out for the inhabitants of the area.

The radiochemical analysis of plutonium activity in urine is the main method for indirect estimation of doses of internal exposure from plutonium incorporation in professional workers. It was previously shown that late-in-life acute diseases, particularly those that affect the liver, can promote accelerated rates of release of plutonium from the liver with enhanced excretion rates. This initial study examines the relationships of some chronic diseases on plutonium excretion as well as the terminal relative distribution of plutonium between the liver and skeleton. Fourteen cases from former workers at the Mayak Production Association (Mayak PA) who provided from 4–9 urine plutonium bioassays for plutonium, had an autopsy conducted after death, and had sufficient clinical records to document their health status were used in this study. Enhanced plutonium excretion was associated with more serious chronic diseases, including cardiovascular diseases and other diseases that involved the liver. These chronic diseases were also associated with relatively less plutonium found in the liver relative to the skeleton determined by analyses conducted after autopsy. These data further document health conditions that affect plutonium biokinetics and organ deposition and retention patterns and suggest that health status should be considered when conducting plutonium bioassays as these may alter subsequent dosimetry and risk models.

Both people and the environment are continuously exposed to sources of radioactivity. Continuous monitoring of the concentration of natural and anthropogenic radioisotopes is of the utmost importance in the estimation of an individual’s received dose. In order to evaluate the radiological safety of locally sourced desalinated water and seafood, the activity concentrations of Cesium-137 (137Cs), Uranium-234 (234U), and Uranium-238 (238U) in Kuwait Bay seawater were measured. Ten 25-L seawater samples were collected from Kuwait Bay and underwent radiochemical analysis. 137Cs levels in the samples were determined by the Ammonium Molybdenum Phosphate (AMP) co-precipitation method, followed by gamma spectrometry measurement. 234U and 238U levels were determined by a radiochemical separation using anion exchange chromatography, followed by an alpha spectrometry measurement. The levels of 137Cs, 234U, and 238U in Kuwait Bay are considered low and comparable to other regional marine water levels. These low levels do not pose a radiological hazard of locally sourced desalinated water and seafood consumption. The ratio of 234U/238U was also calculated in order to investigate the the impact of any anthropogenic sources. These data can be considered a baseline reference for any future comparative analysis, especially since some Gulf countries are initiating their first nuclear reactors within the next few years.

The natural gross radioactivity in milk from farms in different locations in Van and in milk purchased from Kahramanmara markets were determined. In the milk samples, natural gross alpha and beta activity concentrations were measured. The evaporation and ashing procedures were applied to the milk samples collected from farms and markets. Nuclear spectroscopic systems containing gas-flow proportional counters were used to measure the gross alpha and beta activity concentrations of the milk samples. The gross radioactivity in milk from markets was generally lower than the gross radioactivity in milk from farms. The annual effective dose resulting from gross radioactivity for adults, children, and infants and excess lifetime cancer risk values were calculated. The highest total annual effective dose (AED) values were 1,105.9mSvy-1 for adults, 6,456.2mSvy-1 for children, and 10,267.0mSvy-1 for infants in milk samples. The excess lifetime cancer risk (ELCR) values from gross alpha and beta activities range from 0.010 to 3.870 in milk samples.

Radiochemical analysis plays a critical role in the determination of pure beta and alpha emitting radionuclides for environmental monitoring, radioecology, decommissioning, nuclear forensics and geological dating. A remarkable development on radiochemical analysis has been achieved in the past decades to meet the increased requirement. In the recent years, mass spectrometric techniques have been considerably improved and are widely employed for measurement of radionuclides. Analytical methods for rapid, automated and simultaneous determination of radionuclides have been extensively developed for emergency analysis. In Nordic countries, many laboratories are involved in the determination of radionuclides for various purposes, and a series of radiochemical analytical methods have been developed and applied. This article presents the present status and progress on radiochemical analysis of radionuclides, especially in Nordic countries; some requirements from nuclear industries and research organizations, as well as perspectives on the development of radiochemical analysis are discussed.

Radionuclides monitoring is an issue of increasing concern due to their widespread use last years. Thus, efficient methods for radionuclides determination are required. Radionuclides extraction and preconcentration is usually required prior detection, especially when dealing with environmental and biological samples. Most commonly pretreatment techniques in radiochemical analysis are solid-phase extraction and liquid-liquid extraction, providing not only sample clean-up but also high enrichment factors. These protocols are usually long and tedious involving a large consume of reagents and of waste generation what difficult their application in monitoring plans. Flow analysis techniques have proved to be suitable platforms to develop automated radiochemical analyzers, offering advantages such as fast and low-cost methods with low reagents consumption and so waste generation and low manipulation by the analyst. Thus, in this review strategies followed to automate radiochemical analysis exploiting most commonly used pretreatment procedures by flow techniques are presented and critically compared.

The report contains data on specific activity values of natural and artificial radionuclides in the water of underground and surface sources in 19 areas of Russian Federation and data on population internal exposure doses from drinking water consumption in these areas.

Complete dissolution of [(226)Ra]BaSO4 precipitate was successfully performed using NaNO2 as a reducing agent in acidic solution at room temperature. Results showed a significant effect of acid and NaNO2 concentrations and temperature on the dissolution efficiency. The method was successfully used for separation of radium from NORM scale samples from the petroleum industry; sufficient volume reduction of NORM waste was achieved. The obtained (226)Ra solution was purified using two separation methods. The dissolution method can be of great interest in the development of radiochemical analysis of radium isotopes.

The naturally occurring radionuclide 210Po, arising from the uranium–radium decay series, provides a considerable contribution to the radiation exposure to humans. Polonium is analyzed for a variety of purposes, including for radiological impact assessment or as a tracer of environmental processes. Losses of polonium may occur at temperatures above 100 °C, depending on conditions, requiring particular care in sample preparation and treatment. There has been little development regarding analysis of polonium in environmental samples since 1960 as radiochemical analysis of polonium is quite straight forward due to easy of source preparation through auto-deposition on to metal surfaces. In this paper a brief review of estimation of polonium in the soil samples have given emphasis.

An article contains the data on the investigations of season and long-term variations of radiation safety indexes of the water of some underground sources and centralized water-supply system of Tver city.

The extraction-chromatographic behavior of actinium, rare earth elements and other radionuclides formed upon the irradiation of thorium by medium energy protons was studied. The k′ values for Ac(III), Ce(III) and La(III) in nitric acid solutions using Ln Resin, DGA Resin and TRU Resin (Triskem Int.) were determined. The optimal conditions for separation of Ac(III) and rare earth elements (REE(III)) were defined. The obtained results can be used to develop the multipurpose analytical procedure for actinium separation either for the needs of nuclear medicine or for radiochemical analysis of environmental samples.

Plastic scintillation foils of polystyrene and polycarbonate with a thickness between 45 and 200 μm, have been produced using the solvent evaporation method. PSfoils presented a reproducible thickness (10-20%). PSfoils were characterized by the measurement of 36Cl or 241Am. For 36Cl spectrum is located at medium energies since not all energy is deposited in the scintillator and not all betas interact with the foils. For 241Am the efficiency values are very high and spectrum is a sharp peak located at high energies. 222Rn absorption (LD and K) and desorption capacities of the PSfoils have been also evaluated.

We test common fluence diagnostics in the regime of very low burnup natural uranium reactor samples. The fluence diagnostics considered are the uranium isotopics ratios $^{235}$U/$^{238}$U and $^{236}$U/$^{235}$U, for which we find simple analytic formulas agree well with full reactor simulation predictions. Both ratios agree reasonably well with one another for fluences in the mid $10^{19}\,\mathrm{n/cm^2}$ range. However, below about $10^{19}\,\mathrm{n/cm^2}$ the concentrations of $^{236}$U are found to be sufficiently low that the measured $^{236}$U/$^{235}$U ratios become unreliable. We also derive and test diagnostics for determining sample cooling times in situations where very low burnup and very long cooling times render many standard diagnostics, such as the $^{241}$Am/$^{241}$Pu ratio, impractical. We find that using several fragment ratios are necessary to detect the presence of systematic errors, such as fractionation., 7 pages, 4 figures