Radioactivity Monitoring Research Articles

Baseline tritium measurements in Thailand's water bodies: Supporting sustainable nuclear energy development.

Tritium, a radioactive isotope produced naturally through cosmic radiation interactions and anthropogenically through nuclear weapons testing, poses potential environmental risks, particularly within the water cycle. This study measured tritium concentrations in surface water across Thailand to establish a baseline dataset for monitoring potential contamination from nuclear activities and accidents. Surface water samples were collected from 14 large reservoirs during the wet season in October 2023 and the dry season in February 2024, providing a total of 28 samples. Tritium concentrations were analyzed using electrolytic enrichment and liquid scintillation counting techniques. The results, presented with combined uncertainty, revealed tritium levels ranging from 1.21±0.19 to 2.74±0.23 TU (0.14±0.02 to 0.32±0.03 Bq·L-1), with an average of 1.94±0.01 TU (0.23±0.00 Bq·L-1). The highest concentrations were observed in the north (2.26±0.02 TU), followed by the northeast (2.13±0.04 TU), central (1.91±0.05 TU), east (1.72±0.03 TU), and south (1.55±0.04 TU). All measured tritium levels were below the natural background threshold of 10 TU and complied with the surface water quality standards set by the Thailand's Pollution Control Department. Tritium concentrations were positively correlated with latitude, distance from the coast, and elevation, while showing an inverse relationship with pH. No significant seasonal variations or correlations were observed with ion concentrations, water temperature, electrical conductivity, salinity, dissolved oxygen, or total dissolved solids. These baseline measurements are essential for supporting sustainable nuclear energy development and ensuring effective monitoring of environmental radioactivity. The dataset provides a critical reference for Thailand's regulatory agencies, such as the Office of Atoms for Peace, to safeguard public and environmental safety under both normal operations and potential radiological emergency scenarios.

Effect of sampling face velocity on the ultrafine particle surface collection efficiency of a cellulose membrane filter and a cellulose-glass fiber filter for environmental airborne radioactivity monitoring.

Surface collection efficiency (SCE) of a cellulose membrane filter (CMF) and a cellulose-glass fiber filter used in environmental monitoring for alpha-emitting radionuclides from nuclear facilities and natural radioactivity sources was evaluated for particles in the size range of 0.03-0.1μm at different levels of face velocity. The SCE of the CMF was higher than that of the cellulose-glass fiber filter, and only the membrane filter showed the dependence of SCE on the particle size at higher face velocity. The use of the CMF at higher face velocity in environmental radioactivity monitoring leads to measurements of the background alpha spectrum with more degradation under the changing particle size condition in the atmosphere. Consequently, that fact needs to be taken into account, along with the expected particle size distribution and concentration of the airborne radioactivity being sampled, when selecting a face velocity to achieve the best possible detection limit.

Long-Term Investigation (1968–2023) of 137Cs in Apples

Due to the consequences of nuclear and/or radiological accidents in the past (Chernobyl, Fukushima, etc.), and potential future events of that kind, the constant monitoring of environmental radioactivity is important. There are different pathways of the transfer of radionuclides from environment to humans (ingestion, inhalation and external). Food ingestion greatly contributes to the total effective dose; hence, it is of great importance to investigate exposure to radionuclides through food. This paper presents the results of a long-term investigation of 137Cs activity concentration in apples in northwestern Croatia for the period 1968–2023. The highest 137Cs activity concentration in apples was measured in 1986, decreasing exponentially ever since. The Fukushima-Daiichi accident in 2011 did not cause a significant increase in 137Cs activity concentration, although the presence of the consequent fallout was detected via the appearance of 134Cs in some parts of the environment. The observed residence time for 137Cs in apples was estimated to be 4.5 and 3.9 years for the pre-Chernobyl and post-Chernobyl periods, respectively. The correlation between 137Cs in fallout and apples is very good, the correlation coefficients being 0.99, which indicates that fallout is the main source of contamination. The estimated effective dose received by adult members of the Croatian public due to intake of radiocaesium from apples over the overall observed period is 6.4 µSv. Therefore, the consumption of apples was not a critical pathway for the transfer of radiocaesium to humans.

Comparison of quench correction methods for 90Sr/90Y assessment in waters after nuclear incident

One important matter of environmental radioactivity monitoring is the accuracy and precision of the 90Sr/90Y measurement techniques. When Cherenkov counting is carried out in coloured waters, the reduction in detection efficiency can cause significant errors in the obtained results. Two colour quench correction methods were considered in this study: the conventional SCR (Sample Channels Ratio) technique and the Muonic peak method. The latter indicates the quench level via the position of the muonic peak in the cosmic background spectrum. So far, there have been no reports about the Muonic peak method's implementation in Cherenkov counting of 90Sr/90Y in waters. The performance, limitations, advantages, and drawbacks of two methods have been compared based on the analysis of coloured spiked test samples. The Muonic peak method provided similar accuracy as the SCR method in test samples. The adequacy and effectiveness of both techniques have been confirmed during 90Sr routine monitoring in the event of a nuclear emergency or radioactive leakage from nuclear facilities.

A comparative study of the elevated radioactivity in beach placer deposits of Bangladesh.

Beach sediments are mineral deposits formed through weathering and erosion of either igneous or metamorphic rocks. Among the rock constituent minerals are some natural radionuclides that contribute to ionizing radiation exposure on Earth. Kolatoli and Kuakata are the two major beaches with heavy mineral deposits and important tourist sites in Bangladesh. Natural radioactivity in Kolatoli and Kuakata beach sand deposits along the southern coast of Bangladesh was assessed and compared to identify the sources, causes, and possible environmental impact. Result shows most of the radionuclides have higher activity concentrations than the background level, and the activity varies with the sample locations. The dominant radionuclides were found to be the radionuclides of thorium series i.e. Th-232 and Ra-228 followed by uranium series and K-40. The radioactivity in Kolatoli beach sands was observed to be much higher than Kuakata beach due to the presence of a higher content of heavy minerals i.e. illmenite, rutile, zircon, garnet and monazite. Furthermore, monazite and zircon are the two radioactive minerals that are considered to be the main contributors to the radioactivity in Kolatoli beach sand. These minerals are dominated by the activity of thorium series radionuclides i.e. Th-232 and Ra-228 surpass the activity of all other radionuclides such as U-238, U-234, Th-230, Ra-226, Po-210, and K-40. However, major contribution of radioactivity in Kuakata beach sand comes from uranium series radionuclides such as U-238, U-234, Ra-226, and Po-210. Beach morphology, sedimentological, and geochemical evolution of those minerals might be important areas of further study for the radioactivity monitoring activity in those areas.

Radionuclides determination by alpha (210Po, 228,230,232Th) and gamma (226,228Ra, 137Cs, 40K) spectrometry in children's food in Croatia with assessment of cumulative ingestion dose for infants

This work presents comprehensive results of alpha (210Po, 228,230,232Th) and gamma (40K, 226,228Ra, 137Cs) radioactivity measurements in selected food typically consumed by infants (< 1 year) in Croatia. The samples of readily available infant’s food on Croatian market were categorized according to the growth of an infant, from their first nourishment: adapted powdered milk, to their first solid food. The aim was to estimate ingestion doses and the potential radiological risks for infants. In addition to anthropogenic radionuclides, the study focused on naturally occurring radionuclides often underrepresented in similar researches. 40K prevails in activity concentrations in all types of samples. 210Po was determined in all sample types reaching up to 502 mBq/kg. Maximum values of activity concentrations for 228Ra, 226Ra and Th isotopes were 230 mBq/kg, 1.29 Bq/kg and 52 mBq/kg, respectively. The most important contributors to the annual effective dose were 40K, 226Ra, 210Po and 228Ra contributing with 29 % 28 %, 24 % and 17 %, respectively. Th isotopes contributed with less than 2 %, while the contribution of anthropogenic radionuclides 137Cs and 90Sr were negligible (less than 1 %). Cumulative effective ingestion dose for infants was calculated to be 0.69 mSv/y, which is below the recommended limiting dose of 1 mSv/y. Largest proportion comes from the intake of fruit (33 %), followed by the intake of vegetables 19 %) and cereals 19 %). Although national radioactivity monitoring programs usually focus on anthropogenic radionuclides, this study highlights that naturally occurring radionuclides are dominant contributors to the cumulative effective ingestion dose in infants. Overall, the estimated cumulative effective ingestion dose for infants from consuming food available in Croatia is below recommended dose limits and therefore does not present a radiological concern.

Disposition of orally administered atuliflapon, a novel 5-lipoxygenase-activating protein inhibitor in healthy participants.

In this study, the mass balance, pharmacokinetics (PK) and metabolism of atuliflapon, a novel 5-lipoxygenase-activating protein inhibitor, were investigated in healthy male subjects. A single oral dose of 200 mg [14C]atuliflapon suspension was administered to six healthy male subjects. Mass balance, PK and metabolite profiles of atuliflapon were analyzed using radioactivity monitoring and liquid chromatography with mass spectrometry analysis. The safety of atuliflapon was assessed during the study. Atuliflapon was rapidly absorbed with a median tmax of 1.5 h, followed by a biphasic decline in plasma exposure rendering a terminal half-life of ~20 h. Unchanged atuliflapon was the predominant radioactive component in plasma, accounting for 40.1% of the total drug-related exposure (DRE), while a direct N-glucuronide was the only metabolite exceeding 10% of DRE, accounting for 20.9%. Renal excretion of intact atuliflapon accounted for <1% of the administered dose. In total 85.2% of administered radioactivity was recovered over 312 h with 79.3% and 5.9% in feces and urine, respectively. Parent atuliflapon contributed to approximately 40% of the recovered dose in excreta, while metabolites resulting from phase 1 oxidative pathways accounted for more than 30% of the excreted dose. Overall, a single oral dose of 200 mg [14C]atuliflapon suspension was well tolerated in healthy male subjects. The human metabolism and disposition data obtained will support future development and submissions of atuliflapon as a potential candidate drug for the treatment of cardiovascular, cardiorenal, and respiratory indications.

Environmental Radioactivity Monitoring and Radiological Impact Assessment of Agbara Industrial Area, Ogun State, Nigeria

This study assessed the naturally occurring radioactivity of 40K, 238U, and 232Th, which pose a significant threat to human health, particularly when their concentrations exceed the threshold. Background radiation levels were measured at two specific locations, Access Bank and Market areas, across a total of forty (40) sample points. The measurements were taken using a calibrated RS125 Gamma Spectrometer (a portable NaI [Tl] detector) designed in Canada, in conjunction with a global positioning system (GPS) to accurately record the research coordinates within the Agbara industrial area, Ogun State, Nigeria. The mean activity concentrations of the primordial radionuclides were 177.87 Bqkg-1, 20.01 Bqkg-1, and 52.90 Bqkg-1 for 40K, 238U, and 232Th, respectively. More so, the in-situ measured dose rate (DR) ranges between 12.18 nGyh-1 (Access Bank area) and 97.95 nGyh-1 (Market area), with an average value of 47.22 nGyh-1. The average measured and estimated absorbed dose rates were within the safe limit of 57 nGyh-1 provided by UNSCEAR. However, the measured dose rates exceeded the recommended limit in ten locations, while measured activity for thorium exceeded the world average value for over half of the study locations. Although all estimated radiological parameters were within recommended threshold values, suggesting the low risk of exposure to higher levels of ionising radiation in most locations in the Agbara industrial area, there is a potential cancer risk for individuals who have resided in the area for 70 years or more due to long-term exposure to ionising radiation.

Design and application of a shipborne underwater radiation detector array for the monitoring of seawater radioactivity

A navigable online monitoring system for marine radioactivity was developed to cope with possible large-scale marine nuclear pollution incidents. This system used a NaI(Tl) detector array mounted on a ship to collect radioactive data across wide marine areas rapidly. High volume-efficiency aids the system in rapidly identifying radionuclides exceeding standard levels. This feature enables the system to monitor the seawater in a wide area within a shorter time and promptly detect marine nuclear pollution incidents. Monte Carlo simulations were used to optimize the number of NaI(Tl) crystals and the detector spacing for enhancing the volume-efficiency of the system. Three Φ3" × 6″ NaI(Tl) detectors and the mounting bracket with a fixed detector spacing of 30 cm were fabricated based on the simulation outcomes. The volume-efficiency for 137Cs of the system was around six times higher than that for the buoy-based monitoring system with a 3-inch NaI(Tl) detector. The theoretical volume-efficiency curve, which was calculated through Monte Carlo simulation, was verified in a standard liquid source. The minimum detectable activity concentration (MDC) for radioisotopes of the system under various radioactive measurement durations was discussed, such as the MDC for 137Cs for 5 min measurement was 0.152 Bq/L. Marine radioactivity measurement experiments were conducted in the sea near the Tianwan nuclear power plant in Lianyungang, China. The test results showed that the activity concentration of 40K was 11.4 Bq/L. The results of navigation monitoring were consistent with those of sampling and laboratory measurement, which verified the stability and accuracy of the system.

Gross Alpha/Beta Radioactivity of Drinking Water and Relationships with Quality Parameters of Water from Alba County, Romania

Drinking-water is considered one of the existing exposure situations to radiation, which involves a level of risk for human health. Thus, its radioactivity is evaluated to keep exposure “as low as reasonably achievable”. Based on monitoring data sets (2017–2023) for six physical-chemical indicators of drinking water quality and total radioactivity expressed by gross alpha activity, gross beta activity and Radon222 content, we evaluated the correlations, relationships, predictors (water source, locality, year), regional variations and potential baseline patterns using statistical analysis and models. The obtained model shows that drinking water sources and localities are factors with significant effect on nitrates concentration and total hardness, ranking sources in the order: well &gt; spring &gt; municipal distribution system; the rank order of drinking water sources based on the concentration of Radon-222 is spring &gt; well &gt; municipal distribution system; locality was found the best predictor for radioactivity; significant correlations were found between gross alpha and gross beta, between gross beta and Radon-222, and between ammonia, nitrates, nitrites and total hardness. The establishment of a baseline pattern for gross alpha activity is a public health goal that can be achieved through performance monitoring of natural radioactivity in water, useful for preparedness in case of a nuclear event

GROSS ALPHA/BETA ACTIVITY DETERMINATIONIN DRINKING WATER PROFICIENCY TESTS

Water intended for drinking purposes has to be analyzed first for gross alpha/beta activity according to national and international standards and recommendations. According to Albanian legislation, Article 6, the gross alpha/beta radioactivity concentration in water, should be below the level of 0.1 Bq/L and 1 Bq/L respectively for human consumption. Our laboratory participated in an interlaboratory comparison organized by IAEA Terrestrial Environmental Laboratory under suggestion of ALMERA members. Proficiency Test among environmental radioactivity monitoring laboratories for the determination of gross alpha/beta activity concentration in drinking water and contaminated surfaces (2018, 2020). Independent standard methods were used for the reference value determination. Each sample was pretreated on site with nitric acid until reaching a pH level below 2. By creating relatively non-polar surfaces, this procedure avoids a loss of radionuclide fractions due to absorption into the walls of the containers.The Gross alpha/beta activity measurements were done using gas-flow proportional counter (GPC) method. The total dissolved solids should not exceed a surface density of 5 mg/cm2 for gross alpha determination and 10 mg/cm2 for gross beta determination The performance of participating laboratories was evaluated with respect to the reference values using relative deviations. The results presented from our laboratory in both inter comparisons (IAEA-TEL-2018-03) and (IAEA-TEL-2020-03) were all acceptable. The laboratory for the measurement of gross alpha/beta radioactivity and our Institute as a part of Tirana University is in the process of accreditation, so far the participation in the inter comparisons exercise is very important.

Monitoring of the radioactivity in the marine environment: a White Paper - Part I

Radioactivity in the marine environment, although present since the Earth’s formation, is comparatively understudied in contrast to aerial and terrestrial environments. A thorough examination of the radioactivity levels in aquatic environments can establish a robust foundation for comprehending various geochemical processes and phenomena within the water column and near the seabed, and as a result estimate the impact of radioactivity on local ecosystems. To achieve this objective, in-situ, long-term, and continuous monitoring is required. The present part I of the white paper highlights the fundamentals of marine radioactivity, describes the main objectives of an ambitious EU-funded project (RAMONES: Radioactivity Monitoring in Ocean Ecosystems) and introduces the innovative aspects of the technology developed as novel solutions to open problems.

Natural radionuclide profiles and radiological risks in soils and rocks of the Koytash-Ugam Range, Uzbekistan.

This investigation quantifies the activity concentrations of natural radionuclides (226Ra, 232Th, and 40K) in the soils and certain rocks of the Koytash-Ugam Range, Uzbekistan, and assesses their radiological risks. Gamma-spectrometric analysis of soil and rock samples revealed activity concentrations ranging from 456.2 ± 56.0 to 813.9 ± 76.0Bqkg-1 for 40K, 18.2 ± 6.3 to 70.0 ± 12.0Bqkg-1 for 226Ra, and 30.1 ± 2.9 to 57.9 ± 10Bqkg-1 for 232Th. This data indicates a heterogeneous distribution of radionuclides, informing radiation safety and health risk assessments on a global scale. The calculation of radiological hazard indices, including the alpha-index (ranging from 0.09 to 0.35), gamma-index (ranging from 0.40 to 0.73), and both internal (ranging from 0.40 to 0.54) and external (ranging from 0.36 to 0.54) hazard indices, was undertaken to ascertain potential health risks. The radium equivalent activity ranged from 108.4 to 199.3Bqkg-1, and the absorbed dose rates were 51.0-93.3 nGy h-1 indoors and 96.6-178.2 nGy h-1 outdoors. These metrics underlie the estimated annual effective dose of 536.5-988.5 × 10-3mSv y-1, highlighting the variability in radiation exposure. Additionally, the potential lifetime cancer risk was projected at 1770.4 to 3262.0 per million, with an annual gonadal dose equivalent of 361.9 to 655.5 μSv y-1, reflecting natural background radiation influence. The results underscore the importance of safe material use in construction and the necessity for routine natural radioactivity monitoring. Radon flux density (RFD) values within acceptable construction limits (26-176mBqm-2s-1) suggest the area's suitability for development, considering recommended safety guidelines. This study not only aids local environmental and public health frameworks but also enriches the international knowledge base, facilitating comparative studies for the advancement of global radiation protection standards. Through a detailed examination of radionuclide distribution in an under-researched area, our research highlights the critical need for integrated international approaches to natural radiological hazard assessment.

Elevated airborne radioactivity downwind of a Colorado oil refinery

ABSTRACT Airborne radioactivity from fossil fuel production systems is poorly characterized, but a recent study showed elevated ambient levels with proximity to oil and gas production wells. Here, we report year-long, high temporal resolution monitoring results of airborne alpha radioactivity from both radon gas and radon progeny attached to particulates immediately northeast of an oil refinery in Commerce City, Colorado, USA, in an environmental justice community of concern. Gas and particle-associated radioactivity contributed nearly evenly to the total alpha radioactivity. Total radioactivity levels of 30–40 Bq m−3 were 2–3 times higher than background levels (~10–15 Bq m−3) when winds were light and southwesterly, suggesting the refinery as the geographic origin. Furthermore, elevated airborne radioactivity tracked most closely with the light hydrocarbon and natural gas tracer ethane. Thus, the data imply natural gas as the radon emission carrier. Our findings are unique and suggest a need for further investigations of radon emissions from oil and gas infrastructure such as natural gas processing plants, compressor stations, petrochemical plants, and oil refineries that process oil and natural gas from unconventional production. Implications: Regulatory agencies currently do not mandate or conduct monitoring of radioactivity releases and public exposure from petroleum industry air emissions. This study reports elevated radioactivity from radon gas and nonvolatile radon decay products attached to particulate matter, at about 2–3 times above background levels in proximity to Colorado’s largest oil refinery. Observations were within an environmental justice community of concern that experiences well above-average exposure to many other harmful atmospheric pollutants, suggesting potential adverse health effects from this cumulative exposure. Our findings offer actionable insights for policymakers, industry stakeholders, and affected communities alike.

Uncertainty analysis of 137Cs measured by shipborne device for radioactive monitoring

Uncertainty is a crucial indicator of the performance of monitoring devices. Analyzing and calculating uncertainty is a necessary prerequisite for accurately presenting the results of radioactive monitoring for seawater. This paper evaluates the uncertainty involved in the measurement process of the developed radioactive monitoring device. By measuring the different activity concentrations of 137Cs in seawater samples from around a nuclear power plant, and comparing these measurements with radiochemical analysis results. The results show that the main factors affecting the uncertainty of the device are the uncertainty of the γ count rate of seawater sample, the γ count rate and volume of the standard source, with the uncertainty of the γ count rate of seawater sample being the most significant contributor.

Model prediction of radioactivity levels in the environment and food around the world's first AP 1000 nuclear power unit.

Model prediction of radioactivity levels around nuclear facilities is a useful tool for assessing human health risks and environmental impacts. We aim to develop a model for forecasting radioactivity levels in the environment and food around the world's first AP 1000 nuclear power unit. In this work, we report a pilot study using time-series radioactivity monitoring data to establish Autoregressive Integrated Moving Average (ARIMA) models for predicting radioactivity levels. The models were screened by Bayesian Information Criterion (BIC), and the model accuracy was evaluated by mean absolute percentage error (MAPE). The optimal models, ARIMA (0, 0, 0) × (0, 1, 1)4, and ARIMA (4, 0, 1) were used to predict activity concentrations of 90Sr in food and cumulative ambient dose (CAD), respectively. From the first quarter (Q1) to the fourth quarter (Q4) of 2023, the predicted values of 90Sr in food and CAD were 0.067-0.77 Bq/kg, and 0.055-0.133 mSv, respectively. The model prediction results were in good agreement with the observation values, with MAPEs of 21.4 and 22.4%, respectively. From Q1 to Q4 of 2024, the predicted values of 90Sr in food and CAD were 0.067-0.77 Bq/kg and 0.067-0.129 mSv, respectively, which were comparable to values reported elsewhere. The ARIMA models developed in this study showed good short-term predictability, and can be used for dynamic analysis and prediction of radioactivity levels in environment and food around Sanmen Nuclear Power Plant.

Simulation and calibration of radiation monitoring of nuclear power plant containment sump waste liquid

Waste liquid stored in the containment sumps of nuclear power plants may contain a variety of radionuclides. Real-time monitoring of containment sump waste liquid can ensure that accidents, such as leakage of cooling water, can be avoided. This paper presents the design of a radioactive monitoring system for waste liquid in a containment sump. The detector and the lead-shield in the measurement unit are optimized through Monte Carlo simulations. Experimental verification showed that the background count rate of the measurement chamber in the system was 418.3 cps, and the detection limit of the detection system was 3.01 Bq/L. Distinct gamma-ray characteristic peaks were also observable, demonstrating the system's ability to identify radioactive nuclides in the waste.

Establishing a mechanism for international cooperation for Fukushima nuclear-contaminated water monitoring

The Japanese government’s unilateral decision to discharge the nuclear-contaminated water from the Fukushima nuclear power plant into the ocean has caused immense nuclear safety risks. Monitoring the unclear-contaminated water is a starting point to combat these risks and seek remedies for the rights and interests of all concerned parties. The establishment of a mechanism for international cooperation in this respect is necessary to handle the risks of the Fukushima nuclear-contaminated water and to lay the foundation of a framework for tackling any future disposal of nuclear-contaminated water following Japan’s example. At present, the international legal systems in the spheres of nuclear safety and security, marine environmental protection, and other areas, as well as the questioning of the monitoring reports of the International Atomic Energy Agency (IAEA) by the relevant parties, the monitoring practices of historical nuclear accidents, and numerous radioactivity monitoring mechanisms have provided the institutional and practical basis for constructing such a mechanism. The mechanism can be promoted by the IAEA through its existing mechanisms or be jointly initiated by China, the Russian Federation, the Republic of Korea, the Democratic People’s Republic of Korea, and the Pacific Island countries, among other stakeholders. Specifically, this mechanism should consist of three levels: first, the framework of the basic legal system, including the cooperative principles of national sovereignty, interest-relatedness, and procedural fairness, and the signing of the Framework Convention on the Monitoring of Fukushima’s nuclear-contaminated water and its Optional Protocol; second, the organizational structure and its responsibilities, which may include the Conference of Parties as the decision-making body, the Secretariat as the central coordinating body, and the monitoring committees in various fields as specific implementing agencies; and third, specific administrative arrangements, which involve the standardization of monitoring, the management system of monitoring networks and stations, the rules for monitoring procedures, and the rules for the utilization of the monitoring data, etc. With the urgent need for the scientific and fair monitoring of Fukushima’s nuclear-contaminated water, China, as a stakeholder country, can promote the establishment of such a mechanism for monitoring nuclear-contaminated water through the following paths: ① It is necessary to clarify the factors affecting the construction of an international cooperation mechanism for monitoring nuclear-contaminated water so as to ascertain the standpoints of the stakeholders, claims of their interests, contents of their cooperation, and the relevant international relations. ② On the basis of existing practices, China should consider improving the monitoring mechanism to cope with the risks of the discharge of Fukushima’s nuclear-contaminated water by formulating targeted policies and systems, setting up specialized monitoring institutions, and establishing a systematic monitoring network system. ③ This is an effective way for China to actively promote the participation of stakeholders in the construction of an international cooperation mechanism for monitoring nuclear-contaminated water in Fukushima by further innovating the dissemination mechanism to address the risk of Fukushima’s nuclear-contaminated water discharging into the sea and facilitating the identification of issues for international cooperation in monitoring Fukushima’s nuclear-contaminated water based on the concept of a community with a shared future for mankind.

Complex fish migrations call for Fukushima radioactivity monitoring beyond marine systems

Complex fish migrations call for Fukushima radioactivity monitoring beyond marine systems

An overview of automated flow systems for total and isotopic analysis of strontium and yttrium in samples of environmental interest

Due to the different uses of radioactivity during the last decades, there has been an increase in the concentration of natural and artificial radionuclides in the environment. This, along with some accidents with a high affect public opinion (for example, Chernobyl and Fukushima), have led to the growth and establishment of environmental radioactivity monitoring programs. Currently, trends in legislation and research are focused on the development of accurate, precise, reliable and fast analytical methods with low limits of detection (LOD) for radionuclides determination, such as strontium and yttrium, in environmental samples. In this paper, two comprehensive reviews and four automated analytical systems for total and isotopic determination of yttrium and strontium are presented. The developed methods have been applied in the analysis of environmental samples with low concentrations of these analytes. These methodologies have been automated by exploiting flow analysis techniques, such as multi-syringe flow injection analysis (MSFIA), Sequential injection analysis (SIA) and laboratory-on-valve (LOV) systems, achieving a minimal handling and low consumption of samples and reagents, a significant reduction in waste generation and a high frequency of analysis. In the developed methodologies, some spectrometric methods such as ICP-OES and ICP-MS have been implemented as detection techniques instead of radiometric detectors obtaining a fully automated, low-cost and fast yttrium and strontium determinations.