The monitoring of tap waters in Milano: planning, methods and results

Levels, sources, variations, and human health risk assessment of 90Sr and 137Cs in water and food around Sanmen Nuclear Power Plant (China) from 2011 to 2020

Objectives

Radioactivity monitoring around nuclear facilities is crucial to provide important baseline data for effective detection of radioactive leakage to the environment. We aim to establish a baseline study for monitoring radioactive levels of ⁹⁰Sr and ¹³⁷Cs around Sammen Nuclear Power Plant (SNPP) and to assess their associated health impact on surrounding residents.

Methods

In this study, we collected water and food samples around the SNPP from 2011 to 2020 and determined for ⁹⁰Sr and ¹³⁷Cs activity concentrations. We statistically analyzed the temporal trends of ⁹⁰Sr and ¹³⁷Cs and evaluated their radiation exposure to the local residents.

Results

During this period, the activity concentrations of ⁹⁰Sr and ¹³⁷Cs varied within 1.2-9.9 mBq/L and 0.10-7.6 mBq/L in water, and 0.037-1.3 Bq/kg and 0.011-0.45 Bq/kg in food, respectively, with no significant seasonal variation trend.

Conclusions

All reported activity concentrations of ⁹⁰Sr and ¹³⁷Cs were significantly lower than the recommended value of WHO and Chinese national standards. There is no indication of notable radioactive release into the study area due to the operation of SNPP during 2018-2020. The annual effective doses (AEDs) from the ingestion of ⁹⁰Sr and ¹³⁷Cs in water and food were well below the international permissible limits, indicating the radiation exposure around SNPP during 2011-2020 was kept at a safe level.

Assessment of radiation dose hazards caused by radon and its progenies in tap water by the human dosimetric model

Radon is readily soluble in water, and radon exposure caused by household water consumption may pose a threat to public health. In this study, the radon concentration in the tap water of residential buildings was measured, and the average value was 543.33 mBq L^-1, which was in line with the radon concentration limit recommended by USEPA (11.11 Bq L^-1) and EURATOM (100 Bq L^-1), and also within the range of the results of radon concentration measurements in tap water in other countries or regions. Through water bath heating at different temperatures, the radon retention curves of multiple groups of samples at different temperatures were fitted and analyzed. The results showed that the radon retention continued to decrease between 25 and 70 °C, remained stable between 70 and 85 °C, and then continued to decline slowly. Combined with the measurement results, the effective doses of α- and β-particles emitted by ²²²Rn and its progenies to residents respiratory and alimentary tissues and organs were calculated using the computational model provided by ICRP under two typical water scenarios of shower and drinking water, and the results show that radon exposure caused by normal water consumption will not pose a serious threat to public health.

Assessment of radioactivity from groundwater samples from selected areas of Western Black Sea Region, Turkey

In this study, radon concentration measurements and chemical analyses of groundwater samples were performed in four sampling locations of Bartın Province of Western Black Sea Region, Turkey. 222Rn analysis was carried out in groundwater samples with liquid scintillation counting system in accordance with ASTM D5072 standard. The pH, total hardness, alkalinity and dissolved oxygen parameters of the groundwater samples were also determined. The radon concentrations for the water samples ranged between <3.00 Bq/L–12.03 Bq/L. Thirty eight percentage of the samples slightly exceeded the permissible limit of 11.1 Bq/L specified by USEPA for drinking waters. The annual effective doses of groundwater samples were calculated in the range of 7.41–30.74 μSv/y for ingestion of water (E w.Ig ), and in the range of 7.31–30.31 μSv/y for inhalation of radon released from water (Ew.Ih ). The total calculated annual effective doses due to ingestion and inhalation were found to be below the limit value of 100 μSv/y specified by the World Health Organization (WHO). The radioactivity measurement results significantly varied for three sampling points but not for one sampling point on two different measurement dates, which is attributed to the differences in geological structure. The chemical analysis results, except for total hardness in two sampling points, were within the permissible limits specified by international standards.

A review of the analytical methodology to determine Radium-226 and Radium-228 in drinking waters

Radium-228 (228Ra) and Radium-226 (226Ra) isotopes in drinking water are significant from the aspect of radiation protection and human health. In this paper, the three most common preconcentration methods, i.e.coprecipitation, absorption and evaporation, were reviewed with emphasis on routinely measurement techniques. The reviewed measurement techniques include low background γ-spectrometry, α-spectrometry and liquid scintillation counting. The γ-spectrometry technique is the good selection, when the maximum sensitivity is considered. The Environmental Protection Agency guideline has provided the maximum concentration level 0.74 Bq/L for 226Ra and 228Ra. Also, the World Health Organization guideline limit is 1 Bq/L and 0.1 Bq/L for 226Ra and 228Ra, respectively.

Natural radioactivity content in Bulgarian drinking waters and consequent dose estimation

Natural radioactivity in drinking water from Bulgaria was determined in 994 samples. Nine hundred and seventeen of them are from the Southwestern part of the country. The measured activity of natural uranium, (226)Ra, gross alpha and gross beta activity varied from 20 (5) ng l(-1) to 0.11 (3) mg l(-1), MDA to 0.39 (6) Bq l(-1), MDA to 6.23 (39) Bq l(-1) and 0.030 (7) Bq l(-1) to 0.98 (22) Bq l(-1), respectively. Approximately 33% of the investigated waters exceeded a gross alpha activity of 0.1 Bq l(-1), 1.8% a natural uranium concentration of 0.03 mg l(-1) and 1% an (226)Ra concentration of 0.15 Bq l(-1). Annual effective dose from natural radionuclides ranges from 0.0175 (43) µSv to 95.5 (2.6) µSv. Median values of the contribution of the (226)Ra and uranium to the indicative dose are 10.22 and 0.21 µSv y(-1), respectively. Poor relationships between (226)Ra/nat.U (r, 0.12) and for gross beta activity/natural uranium (nat.U) (r, 0.29) were observed. The relationships between nat.U/gross alpha activity (r, 0.50) and for gross alpha activity/gross beta activity (r, 0.52) concentration distributions were stronger.

Radioactivity of drinking-water in the vicinity of nuclear power plants in China based on a large-scale monitoring study

The public concern for radioactivity of drinking-water has been increasing in recent years after the rapid development of nuclear power plants, and especially after the Fukushima nuclear accident. In this study, the radioactivity of water samples collected in the vicinity of nuclear facilities from seven provinces in China was measured and an average annual equivalent effective dose derived from drinking-water ingestion was calculated. The results showed that, in winter and spring, the activities of gross α and β ranged from 0.009 Bq/L to 0.200 Bq/L and from 0.067 Bq/L to 0.320 Bq/L, respectively. While, in summer and autumn, the activities of gross α and β varied from 0.002 Bq/L to 0.175 Bq/L and from 0.060 Bq/L to 0.334 Bq/L. Our results indicated that the gross α and β activities in these measured water samples were below the WHO recommended values (0.5 Bq/L for gross α and 1.0 Bq/L for gross β) and the annual equivalent effective dose derived from drinking-water ingestion was at a safe level.

Determination of radon and radium concentrations in drinking water samples around the city of Kutahya

The concentration of radium and radon has been determined in drinking water samples collected from various locations of Kutahya city, Turkey. The water samples are taken from public water sources and tap water, with the collector chamber method used to measure the radon and radium concentration. The radon concentration ranges between 0.1 and 48.6±1.7 Bq l(-1), while the radium concentration varies from a minimum detectable activity of <0.02-0.7±0.2 Bq l(-1) in Kutahya city. In addition to the radon and radium levels, parameters such as pH, conductivity and temperature of the water, humidity, pressure, elevation and the coordinates of the sampling points have also been measured and recorded. The annual effective dose from radon and radium due to typical water usage has been calculated. The resulting contribution to the annual effective dose due to radon ingestion varies between 0.3 and 124.2 μSv y(-1); the contribution to the annual effective dose due to radium ingestion varies between 0 and 143.3 μSv y(-1); the dose contribution to the stomach due to radon ingestion varies between 0.03 and 14.9 μSv y(-1). The dose contribution due to radon inhalation ranges between 0.3 and 122.5 μSv y(-1), assuming a typical transfer of radon in water to the air. For the overwhelming majority of the Kutahya population, it is determined that the average radiation exposure from drinking water is less than 73.6 µSv y(-1).

Serratia sp. ZF03: an efficient radium biosorbent isolated from hot-spring waters in high background radiation areas

The aim of this study is to isolate and characterize (226)Ra biosorbing indigenous bacterial strains from soils and hot-springs containing high concentrations of (226)Ra by using biochemical and molecular approaches. Fifteen bacteria were isolated and their phylogenetic affiliations were determined based on their 16S rRNA gene and the two most relevant hypervariable regions of this gene; V3 and V6 analysis. A pigmented Serratia sp. ZF03 strain isolated from the water with (226)Ra content of 50471 mBq l(-1), caused 70% removal of (226)Ra at a radioactivity level of 50 Bq ml(-1), after 5 min and 75-80% in equilibrium time of 1 h, depending on the particular biosorption system and experimental conditions studied. The biosorption equilibrium was described by Langmuir and Freundlich isotherm models. Kinetic studies indicated that the biosorption follows pseudo-second-order kinetics. Effect of different physico-chemical parameters on (226)Ra sorption, FTIR, SEM and TEM analysis were also investigated.

Radioactivity measurements and radiation dose evaluation in tap waters of Central Italy

Consumption of drinking water is very important for human nutrition and its quality must be strictly controlled. A study of radioactivity content in tap water samples collected in the Central Italy was performed in order to check the compliance with recent European regulations. Gross alpha and beta activity, 226Ra, 238U and 234U concentrations were measured. Gross alpha and beta activities were determined by standard ISO 9696 and ISO 9697; for 226Ra determination liquid scintillation was used. 238U and 234U concentrations were determined by alpha spectrometry after separation from matrix by extraction chromatography and electroplating. Recommended WHO guideline activity concentrations for drinking water (0.1 and 1.0 Bq/L for gross alpha and gross beta activity, respectively) are exceeded in two cases for gross alpha activity and are not exceeded in any case for gross beta activity. The concentrations (mBq/L) of 226Ra, 238U and 234U ranged from <1.70 to 15.3, 0.65 to 48.8 and 0.780 to 51.5, respectively. Effective dose due to the uranium isotopes and radium was calculated for children and adults using the dose coefficients reported by EC Directive 96/29 EURATOM and annual water intake. For all class ages, the doses are quite similar and much lower than 0.1 mSv/year.

Natural radionuclides measurements and total dose indicative evaluation in drinking waters of an Italian central region

A study of radioactivity content in drinking waters collected in some areas of geological interest in an Italian central region was performed to check the compliance with recent European regulations. Gross alpha and beta activities, 226Ra, 238U, 234U, 210Po and 3H concentrations were measured. Gross alpha and beta, 226Ra and 3H activities were determined using an ultra-low-level scintillation counter, 238U, 234U and 210Po by alpha spectrometry after radiochemical separation. Recommended WHO guideline activity concentrations for drinking water were exceeded in 6 cases for gross alpha activity and were not exceeded in any case for gross beta activity. Tritium concentration was always lower than MDA (6.75 Bq L(-1)); the concentrations (mBq L(-1)) of 226Ra, 238U, 234U and 210Po ranged from <1.80 to 23.00, from 1.20 to 140.00, from 1.60 to 120.00 and from 0.25 to 5.90, respectively. Due to the importance of the water in human diet, the doses were calculated for children and adults using the dose coefficient factors reported by EC Directive 96/29 EURATOM and annual water intake; all samples furnished a dose lower the reference level for drinking water (0.1 mSv y(-1)).

(238)U, (234)U, (226)Ra, (210)Po concentrations of bottled mineral waters in Italy and their dose contribution

Due to the importance of bottled mineral water in human diet with special regard to children in lactation period, a monitoring of natural radioactivity in some bottled mineral waters produced in Italy was performed. Gross alpha and beta activities and (226)Ra, (238)U, (234)U, and (210)Po concentrations were measured. Gross alpha and beta activities were determined by standards ISO 9696 and ISO 9697; for (226)Ra determination liquid scintillation was used. The (238)U and (234)U concentrations were determined by alpha spectrometry after their separation from matrix by extraction chromatography and electroplating. (210)Po was measured by alpha spectrometry. The results revealed that the concentrations (mBqL(-1)) of (226)Ra, (238)U, (234)U, and (210)Po ranged from <10.00 to 52.50, from <0.17 to 89.00, from <0.17 to 79.00, and from <0.04 to 21.01, respectively. Uranium and radium concentrations do not reach the relevant recommended derived activity concentration (DWC). For polonium concentration, none of the samples reaches the relevant DWC in the case of adults and children, but one sample exceeds this value for infants. The dose contribution for different classes of age was calculated using the dose coefficient factors reported by EC Directive 96/29 EURATOM and certain annual intake. For children and adult age class, the calculated doses are quite similar and lower than 0.1mSvy(-1); for infants (<1y) in three cases the calculated dose ranges from 0.11 to 0.17mSvy(-1).