Estimation of daily uranium ingestion by urban residents in Japan

125 types of food were collected mainly from Yokohama City which is one of the typical urban cities in Japan. The samples, were divided into the 18 food categories in the report of the National Nutrition Survey (NNS),¹ were analysed for uranium by -spectrometry after chemical separation. Concentrations of²³⁸U in individual types of food ranged from 9.85·10^–5 Bq·kg^–1 in grain vinegar to 5.90 Bq·kg^–1 in boiled and dried hijiki. The median value of²³⁸U was found to be 4.83·10^–3 Bq·kg^–1 on a raw weight basis. The daily intake of²³⁸U per person by ingestion was estimated to be approximately 14 mBq with more than 50% of it coming from marine products.     

137Cs in Biota and Sediment Samples from Turkish Coast of the Black Sea, 1997–1998

During the periods of 1997–1998, macroalgae, sea snail, mussel, fish and sediment samples were collected from different stations at Turkish Black Sea coast in order to determine activity levels of ¹³⁷Cs radionuclide. ¹³⁷Cs activity in the tested algae species and in soft parts of mussel and sea snail, were found to be below the lower limit of detection. On the other hand, the ¹³⁷Cs concentration in muscle tissue of the sea snail samples were found from 6±2 to 19±7 Bq·kg^–1 dry weight. The range of the ¹³⁷Cs concentration in anchovy fish muscles were found between 4±2 – 10±5 Bq·kg^–1 dry weight. The ¹³⁷Cs concentration in the whiting fish muscle was found below the lower limit of detection. However, this activity found in shad fish muscle to be 25±10 Bq·kg^–1 dry weight. The concentrationsof the ¹³⁷Cs activity in the sediment samples proved that the eastern region of the Black Sea was affected by Chernobyl at a very high degree compared with the western part. The measured ²³⁸U, ²³²Th and ⁴⁰K concentrations in sediment samples are within the range of the cited values in the previous works at the Turkish Black Sea coast.     

Use of Extraction Chromatography, Ion Chromatography and Liquid Scintillation Spectrometry for Rapid Determination of Strontium-89 and Strontium-90 in Food in Cases of Increased Release of radionuclides

For rapid determination of ⁸⁹Sr and ⁹⁰Sr in food, isocratic ion chromatography used for Sr isolation and purification is integrated in a complete analytical system comprising sample preparation, incineration, dissolution, phosphate precipitation for alkali/alkaline carth separation, and Sr specific extraction chromatography on crown ether basis for Ca/Sr separation. Strontium-89 and ⁹⁰Sr are determined by liquid scintillation spectrometry after carbonate precipitation. The components of the mixed spectra obtained are calculated by the computerized spectra subtraction method. Two days plus measuring time are required for single, three for double analysis. The limit of detection for ⁸⁹Sr and ⁹⁰Sr is ca. 0.1 Bq·kg^–1, related to the fresh produce.     

Long-Lived Radionuclides in Sea Sediments Around Kashiwazaki-Kariwa Nuclear Power Station

Natural and artificial radionuclide concentrations in sea sediments around Kashiwazaki-Kariwa nuclear power station have been investigated with respect to the particle size distributions and the ignition losses during assay. Plutonium concentrations around the south and north discharge area, ranged from 0.054 to 0.24 Bq·kg^-1 (average 0.145) and 0.15 to 0.25 Bq·kg^-1 (average 0.213), respectively. Plutonium concentrations were significantly related to erosion and accumulation processes of sediments in both south and north discharges. Additionally, the ratios of ²³⁹Pu to ²⁴⁰Pu were evaluated with ICP-MS to determine the origin of the Pu-isotopes. Uranium-238, ²³²Th and ⁴⁰K were found in concentration range of 7.3–67, 12–100 and 260–560 Bq·kg^-1 with mean concentrations of 20, 29 and 390 Bq·kg^-1, respectively. It is assumed that the relatively high concentrations of the natural radionuclides such as U and Th are due to the presence of minerals (the south discharge regions). On the basis of these results, the origin of the Pu-isotopes was assumed to be derived from fallout of the past atmospheric nuclear tests.     

Natural radioactivity in some building materials and by-products of Shaanxi, China

The concentration of ²²⁶Ra, ²³²Th and ⁴⁰K has been determined by -ray spectrometry. The measured activity in the selected building materials and by-products of coal fired power plants ranges from 21.5 to 91.3 Bq·kg^–1, 15.4 to 63.2 Bq·kg^–1 and 83.2 to 683.9 Bq·kg^–1 for ²²⁶Ra, ²³²Th and ⁴⁰K, respectively. The results were compared with the reported data of other countries and with the world average activity of soil. The radium equivalent activities values of all building materials are lower than the limit of 370 Bq·kg^–1, equivalent to a -dose of 1.5 mSv·y^–1. The values of the external hazard index and the internal radiation hazard index are less than unity.This work was supported by the Provincial Natural Sciences Foundation of Shaanxi through Grants 2003D04 and by the Science Foundation of Shaanxi Normal University. Gratitude is expressed to J. Xiaowei, W. Xiaolei, L. Zhendong for assisting in sampling.     

Analysis for naturally occuring radionuclides at environmental concentrations by gamma spectrometry

The analytical potential of low level, high resolution gamma-ray spectrometry for naturally occurring radionuclides at environmental levels is described, with particular emphasis on detector background levels and sensitivity. Comparisons are drawn between the performance of a specially designed low background detector system, and that of standard off the shelf devices. Sample characteristics, calibration procedures and checks, are described, and empirical minimum detection limits of between 0.4 Bq·kg^–1 (²²⁶Ra,²²⁸Th) and 10 Bq·kg^–1 (²¹⁰Pb) are derived for soil or sediment samples of about 250 g. Representative analyses of a variety of environmental samples, including water, plant material, animal tissue and sediment, are given to illustrate the routine use of the spectrometer.     

Natural radioactivity in some building materials and by-products of Shaanxi, China

The concentration of ²²⁶Ra, ²³²Th and ⁴⁰K has been determined by -ray spectrometry. The measured activity in the selected building materials and by-products of coal fired power plants ranges from 21.5 to 91.3 Bq·kg^–1, 15.4 to 63.2 Bq·kg^–1 and 83.2 to 683.9 Bq·kg^–1 for ²²⁶Ra, ²³²Th and ⁴⁰K, respectively. The results were compared with the reported data of other countries and with the world average activity of soil. The radium equivalent activities values of all building materials are lower than the limit of 370 Bq·kg^–1, equivalent to a -dose of 1.5 mSv·y^–1. The values of the external hazard index and the internal radiation hazard index are less than unity.This work was supported by the Provincial Natural Sciences Foundation of Shaanxi through Grants 2003D04 and by the Science Foundation of Shaanxi Normal University. Gratitude is expressed to J. Xiaowei, W. Xiaolei, L. Zhendong for assisting in sampling.     

Radiochenical determination of technetium-99 in LLW by chelation with sodium diethyl dithiocarbamate (NaDDC) and extraction with chloroform

A radiochemical method has been developed for the determination of⁹⁹Tc in low-level radioactive, waste from nuclear facilities, using^99mTc as an internal tracer. Radioactive contaminants were removed by carrier hydroxide precipitation and chelating extraction with NaDDC/CHCl₃ system at pH 4. The final technetium was chelated with NaDDC in 3N HCl solution and extracted selectively into chloroform. The average of radiochemical recovery for various types of LLW sample is about 90%. The decontamination factors for most radioactive nuclides are higher than 10⁵. The detection limit for⁹⁹Tc in a sample of about 10 g is 0.17 pCi/g (6.5 Bq·kg^–1) for a 100-minute count.     

Rapid determination of90Sr by Compton suppression gamma-ray spectrometry

This work presents a low-level background gamma spectrometry system capable of achieving rapid determination of⁹⁰Sr without chemical separation, in a soil sample when the⁹⁰Sr to -ray emitting nuclide concentration ratio exceeds 10. The system consists of a highly efficient HPGe central detector operated in coincidence or anticoincidence with a NaI(Tl) guard detector and a NaI(Tl) backscatter detector. Experimental results indicate that the bremstrahlung radiation from a pure -emitter can be distinguished with respect to the differences in normal and coincidence spectra. The⁹⁰Sr activity can be directly detemined in the sample in less than 1 hour with a minimum detectable concentration (MDC) estimated at 0.002 Bq·g^–1 for a sample containing no appreciable -ray nuclides or other high energy, -emitting nuclides. In actual measurement, a 0.06 Bq·g^–1 MDC for contaminated soils is achieved.     

Depth distribution of239,240Pu and137Cs in soils of South Korea

Depth distribution of^239,240Pu and¹³⁷Cs in the soils of South Korea have been studied. The average accumulated depositions were estimated roughly to be 54.8±32.1 Bq·m^–2 for^239,240Pu, 1.6±1.0 Bq· ·m^–2 for²³⁸Pu and 1982.8±929.1 Bq·m^–2 for¹³⁷Cs. The activity ratios of^239,240Pu/¹³⁷Cs in soils were found to be in the narrow range of 0.0153 to 0.0364 with a mean value of 0.0230±0.006. The concentrations of^239,240Pu and¹³⁷Cs in soils decrease exponentially with increasing the soil depth. A significant correlation was found between the concentration of^239,240Pu and that of¹³⁷Cs. The activity ratios of^239,240Pu/¹³⁷Cs tend to increase slightly with increasing soil depth.     

Analysis of210Po in marine samples

A method for determining²¹⁰Po in marine samples by wet dissolution, deposition onto silver disc and counting by -spectrometry is described. Recovery of polonium was obtained with²⁰⁸Po tracer.²¹⁰Po levels in fish from the Brazilian coast and sediments from Antarctic region were determined. Levels in fish ranged from 0.5 to 5.3 Bq·kg^–1 wet and for sediments, mean values of 10 mBq·kg^–1 were obtained.     

Levels of210Po in some beverages and in tobacco

The objective of the present work is the estimation of the²¹⁰Po content in some beverages and in tobacco, in order to assess the corresponding collective doses to the population in Argentina. Yerba mate, tea leaves, their infusions and ground coffee were analyzed, as well as tobacco. Collective doses due to the annual consumption of the beverages described were found to be from 6 man.Sv to 1200 man.Sv. Results for²¹⁰Po in tobacco ranged from 10 Bq·kg^–1 to 80 Bq·kg^–1. Lung doses due to the use of tobacco vary from 75 Sv·y^–1 to 600 Sv·y^–1.     

Variation of natural232Th excretion in non-exposed persons

Urinary excretion of²³²Th was assessed, in occupationally non-exposed persons by means of inductively coupled plasma-mass spectrometry (ICP-MS). Measurements were performed in 55 healthy subjects. Mean daily²³²Th excretion was 47±26 Bq·d^–1 (range 17–121 Bq·d^–1). Results obtained showed no statistically significant correlation with age and no differences were found between males and females. The impact on the assessment of intakes by workers is discussed.     

Deposition of gamma-emitting nuclides in Japan after the reactor-IV accident at Chernobyl'

The wet and dry deposition of gamma-emitting nuclides are presented for Tsukuba and eleven stations in Japan following the nuclear reactor accident at Chernobyl'. In Japan fallout from the reactor at Chernobyl' was first detected on May 3, 1986, a week after the accident. Abruptly high radioactive deposition, which mainly consists of¹³¹I,¹³²I,¹⁰³Ru,¹³⁷Cs and¹³⁴Cs, was observed in early May. The cumulative amount of¹³¹I,¹⁰³Ru and¹³⁷Cs in May at Tsukuba were 5854±838 Bq·m^–2, 364±54 Bq·m^–2 and 130±26 Bq·m^–2 (decay was corrected to April 26), respectively. The monthly¹³⁷Cs deposition in May corresponds to 2.5% of the cumulative¹³⁷Cs deposition during the period from 1960 through 1982. Most of the Chernobyl' radioactivities, especially¹³¹I, are scavenged from the atmosphere by the wet removal process.     

Measurement of Gamma-Dose Caused by Built in Coal Slags with Elevated 226Ra Concentration, and the Modelling of Shielding

Slags, derived from coal mined in the neighbourhood of the town Tatabánya in Hungary, have been used as filling and insulating material for buildings of houses, block of flats, schools and kindergartens. The slag samples come from here have elevated concentrations of ²²⁶Ra, (range of 850–2400 Bq·kg^–1). Therefore, the external gamma dose rates at 1 m height were about four times higher than the world average. It has been found, based on the modelling, that the dose rate could be decreased with 70–80% using an appropriate thickness of concrete or barite-concrete layers.     

Plutonium and cesium isotopes in river waters in Japan

Concentrations of cesium isotopes and plutonium in river water samples in Japan, collected during the period from June 1985 to February 1987, have been measured. The total¹³⁷Cs concentrations in the Japanese river waters ranged from 0.063 to 1.89 mBq·l^–1. The portion of particulate¹³⁷Cs to total was observed to be less than 10 to 35%. The total^239,240Pu concentrations ranged from 0.56 to 1.93 Bq·l^–1. Particulate^239,240Pu occupied 13 to 95% of the total. After the Chernobyl fallout, elevated¹³⁷Cs concentrations were observed in the Japanese river waters as well as the detection of¹³⁴Cs, whereas there was no effect on the river plutonium from the Chernobyl fallout. The partition coefficients of¹³⁷Cs and plutonium between suspended particulate and dissolved phases in the Japanese rivers were determined: from 1.0·10⁴ to 3.2·10⁵ and from 4.1·10⁴ to 2.3·10⁶ for¹³⁷Cs and plutonium, respectively. The result suggests that these radionuclides, especially plutonium, are tightly associated with soil particles and/or suspended matter.     

Heliuim-3 mass spectrometry for low-level tritium analysis of environmental samples

Helium-3 (³He) mass spectrometry for the analysis of low-level tritium (³H) concentrations (0.5 to 5 Bq·l^–1) in environmental sample matrices was compared with conventional low-level -decay counting methods. The mass-spectrometry method compared favorably, equalling or surpassing conventional decay-counting methods with respect to most criteria. Additional research and method refinements may make³He mass spectrometry the method of choice for routine, low-level to very-low-level (L<0.5 Bq·l^–1)³H measurements in a wide variety of environmental samples in the future.     

Simultaneous analysis of 137Cs, 90Sr, 238Pu and 239+240Pu in Brazilian seawater

Methodologies for simultaneous analysis of ¹³⁷Cs, ⁹⁰Sr, ²³⁸Pu and ^239+240Pu were developed and applied to seawater samples. ¹³⁷Cs levels in Brazilian coastal seawater ranged from 0.12 to 4.7 Bq·m^-3, for ⁹⁰Sr from 2.0 to 8.6 Bq·m^-3, for ^239+240Pu from 0.8 to 4.5 mBq·m^-3 and for ²³⁸Pu it was of 1.9 mBq·m^-3. The artificial radioactivity levels in Brazilian seawater are typical values due to fallout deposition.     

<Superscript>3</Superscript>H and <Superscript>90</Superscript>Sr in urine radiobioassay intercomparison results from the intercomparison studies program at Oak Ridge National Laboratory: statistical analysis of laboratory performance

The Intercomparison Studies Program (ISP) at the Oak Ridge National Laboratory (ORNL, Oak Ridge, TN USA) provides natural-matrix human urine quality-assurance/quality-control (QA/QC) samples to radiobioassay analysis laboratories. Samples are provided to these laboratories as “single-blind” or “double-blind” unknowns, spiked with radioactive-solution standards at “low” levels (e.g., 0.7–7 Bq g⁻¹ for ³H and 0.7–7 Bq kg⁻¹ for ⁹⁰Sr). Participants use the results as a tool for self-evaluation and a measure of performance. In this paper, sample preparation and the results of testing during the years 2001–2005 for ³H and ⁹⁰Sr are presented and discussed.     

Precipitation separation of strontium and calcium from acidic solutions using crown ether and tungstosilicic acid

Strontium forms a compound of composition (SrL)₂A·nH₂O with low solubility (5.0·10^–6 mol Sr·dm^–3) in the presence of 18-crown-6 (L) and tungstosilicic acid (H₄A) in acid media, as has been found by radiometric precipitation titration. Formation of the compound with limited solubility was used for separation of strontium and calcium from 1 mol·dm^–3 HCl. It is possible to separate strontium in the range from trace to 6 mmol·dm^–3 in the presence of calcium with its concentration up to 0.2 mol ·dm^–3 and the recovery determined was 95% of Sr and 5% Ca or 90% of Sr and 4% Ca, respectively. The ratio of Sr/Ca depends on the stability constants ratio of metal-L (⊃_SR/⊃_ca) in the case of gradual addition of L. Potassium up to the concentration of 0.05 mol·dm^–3 does not influence recovery of strontium.