UPTAKE AND DISTRIBUTION OF RADIOSTRONTIUM IN TOMATO TREATED WITH ARBUSCULAR MYCORRHIZAL FUNGI.

Arbuscular mycorrhizal fungi (AMF) were inoculated into the root system of edible tomato plants to investigate their effect on the uptake and distribution of strontium radionuclide in the tissues of plants grown under laboratory conditions. The experiments were carried out in a sterile mixture of topsoil and sand, where in one series of experiments contaminated soil with 85Sr was used. Seeds were inoculated with a mixture of AMF at sowing, the second, control series was without application of AMF. Determination of radioactivity in soil and in different parts of tomato plants was carried out by gamma-spectrometric measurement. The obtained results and statistical analysis indicated a significant association between AMF inoculation of plants and the change in the distribution of 85Sr. The presence of AMF reduced the translocation of 85Sr from the root system to the aerial parts of tomato plants.

Synergy of flow injection system and molecular recognition technology products for rapid determination of 89,90Sr and 210Pb.

A rapid, automated separation procedure was developed for radioactive strontium and lead isotope determination. This system includes a portable automated system for the preconcentration and sequential elution of targeting isotopes with an Na2H2EDTA solution from solid phase extraction materials, AnaLig®Sr-01 and SuperLig®620, provided by IBC Technologies. Strontium and lead were separated from the majority of matrix constituents to obtain pure fractions of Pb and Sr prior to radiometric detection. In case of barium presence, it can also be fully isolated and completely separated from Sr. The automated procedure can be successfully used for preconcentration and separation from high as well as low radioactivity samples. With only a 1 mL column filled with SuperLig®620, it is possible to isolate Sr and Pb with 100% recovery from 1 L to 2 L of sample at a flow rate of up to 10 mL min-1 within several hours. 89,90Sr isotopes can be further determined by Cherenkov counting, while 210Pb isotopes can be determined by either gamma spectrometry or liquid scintillation counter. The method was tested and validated using certified standard materials and proficiency test samples. The synergy of automated separation and detection procedures enables the determination of the low level activity of 90Sr and 210Pb in a short time with detection limits of 20 mBq L-1 for both isotopes. The proposed method enables lower labour costs, minimal size of apparatuses and columns, low separation time, and reduced secondary waste production. The automated procedure may be easily implemented in laboratories worldwide and can also be used at sampling sites.

Determination of 79Se using a volatilisation method and liquid scintillation spectrometry.

The operation of nuclear power plants generates large quantities of radioactive materials or waste, which need to be characterised before decommissioning or for final disposal in radioactive waste repositories. The nuclear operators in Slovakia must declare 19 critical radionuclides in all radioactive waste before storage in the regional waste repository. This article describes a simple and rapid method for the determination of one critical radionuclide, 79Se, in radioactive waste. The conditions for the effective distillation of selenium from various mixtures of HCl and HBr solutions were studied. The highest selenium recoveries were achieved in a mixture of 6.5 mol L-1 HCl and 18.3 mol L-1 HBr in 7:1 vol ratio. The method was applied for the determination of 79Se in radioactive concentrates and sludge samples from nuclear power plants in Slovakia. 79Se was measured with a TRI CARB 3100 TR liquid scintillation counter.

Preparation and characterization of MnO2- SiO2 composite resin for 226Ra pre-concentration in water samples.

The presented work describes an effective method for 226Ra determination using laboratory- prepared MnO2-SiO2 composite resin. Samples were traced with 133Ba for radium radiochemical recoveries monitoring which were in the range of (77 - 100%). MnO2- SiO2 composite resin was used to collect for 226Ra from water samples (pH = 6.5-7.0). Radium was eluted from the column with 50 mL of 4 mol L-1 HNO3 at a flow rate of 1.5 mL min-1. Alpha-spectrometric counting of Ba(Ra)SO4 microprecipitate was used for 226Ra determination. The new developed method was used to the 226Ra determination in samples of natural mineral, mountain spring, drinking and natural healing waters from Slovakia and Czech Republic.

Comparison of different methodologies for the 90Sr determination in environmental samples.

The paper describes different isolation/separation and detection procedures for 90Sr determination in the environmental samples which are routinely used in Laboratories A and B. In this context, four different methods for strontium isolation and two methods for detection were tested and compared by 90Sr determination in proficiency test samples (water, soil, vegetation) and animal bone samples. The chromatographic isolation of Sr on Sr resin, AnaLig®Sr01 resin gel, strong base anion exchange resins in nitrate form and combination of strong base anion exchange and Sr resin were used for the examination of the impact of sample matrix constituents on efficiency of strontium isolation (chemical yield), while Cherenkov counting of 90Y and counting of 90Sr(90Y) on proportional counter were used for the quantitative 90Sr determination. The chemical yields obtained with different isolation methods were compared with the emphasis on its influence on reliability of the 90Sr determination in different kinds of samples. The results show that the efficiency of strontium isolation depends on type of sample and separation methodology. The strontium yield on Sr resin column decreases with the increase of Sr, Ca and Na concentration. In the presence of 1 g of Ca and 1 g of Na, the yield of 85% was obtained for 5 mg of Sr carrier and dropped below 50% with further increase of Sr and other elements. However, the yield can be increased to 75% if Na and part of Ca are separated from Sr on the anion exchange column with alcoholic solution of nitric acid and by final separation of Ca from Sr on the Sr resin column. In the presence of large amounts of Ca, Na and other elements, isolation efficiency on the Sr resin column significantly decreases in comparison with other methods. The average yield for isolation from vegetation samples on the Sr resin column is only 21%. For the soil samples the highest average yield (78%) is obtained for the isolation in the combination of anion exchange and Sr resin columns. For the isolation from bone samples the average yields over 80% are on AnaLig®Sr01 and anion exchange resins columns, while Sr resin was not used for separation due to high content of Ca in samples. The results of the 90Sr determination in proficiency testing (PT) samples show that the accuracy of the determination does not depend on high chemical yield but depends on accuracy of yield determination. The analysis of z-values shows that 96% of obtained z-values range from 0 to ±2 while 77% of z-values range between 0 and ± 1. Ninety percent of obtained results of 90Sr determination deviate less than 20% from assigned values in PT provider reports. The results of 90Sr determination in animal bone samples using different methods are in good agreement. The results obtained by Cherenkov counting in both laboratories vary from -3.1-14.5% while results obtained by determination via 90Y and counting on i-Matic vary between -10.0 and -2.9%. These deviations are in accordance with deviations obtained with PT samples. Activity concentrations of 90Sr in wild boar bone samples range from 4 to 30 Bq kg-1 while in deer bone samples from 2 to 8 Bq kg-1.

Development of 126Sn separation method by means of anion exchange resin and gamma spectroscopy.

This paper describes a method employing anion exchange resin for determination of 126Sn in radioactive waste. The method is suitable for the separation of 126Sn isotope from hydrochloric and hydrofluoric acid solution. The separation is based on precipitation of tin with ammonium sulfide in 0.5molL-1 HCl, dissolution of the precipitate in concentrated HCl, loading in 2molL-1 HCl onto anion exchange resin column and elution with 2molL-1 HNO3. 126Sn was measured by gamma spectrometry.

Separation techniques for quantification of radionuclides in environmental samples.

The reliable and quantitative measurement of radionuclides is important in order to determine environmental quality and radiation safety, and to monitor regulatory compliance. We examined soil samples from Podunajske Biskupice, near the city of Bratislava in the Slovak Republic, for the presence of several natural ((238)U, (232)Th, (40)K) and anthropogenic ((137)Cs, (90)Sr, (239)Pu, (240)Pu, (241)Am) radionuclides. The area is adjacent to a refinery and hazardous waste processing center, as well as the municipal incinerator plant, and so might possess an unusually high level of ecotoxic metals. We found that the levels of both naturally occurring and anthropogenic radionuclides fell within the expected ranges, indicating that these facilities pose no radiological threat to the local environment. During the course of our analysis, we modified existing techniques in order to allow us to handle the unusually large and complex samples that were needed to determine the levels of (239)Pu, (240)Pu, and (241)Am activity. We also rated three commercial techniques for the separation of 90Sr from aqueous solutions and found that two of them, AnaLig Sr-01 and Empore Extraction Disks, were suitable for the quantitative and reliable separation of (90)Sr, while the third, Sr-Spec Resin, was less so. The main criterion in evaluating these methods was the chemical recovery of (90)Sr, which was less than we had expected. We also considered speed of separation and additional steps needed to prepare the sample for separation.