Rapid determination of131I in environmental waters using a liquid anion exchanger

A rapid and specific method for the determination of¹³¹I in environmental water samples in the presence of some of the most important fission products is described. Radioiodine is separated from acidified water using tri-n-octylamine solution in toluene with dissolved iodine by one-stage static procedure with about 90% separation efficiency and 200-fold volume concentration. After the decolorization of the organic phase with NaOH in methanol, radioactivity of¹³¹I is counted by a toluene base liquid scintillator with a counting efficiency of 70%. The method is simple and enables to determine low radioactivity¹³¹I with a detection limit less than 5 pCi/1 in about 1.5 hrs.     

Possibilities of the determination of3H,14C and131I individually and in mixtures,by the method of amplitude attenuation using liquid scintillators

Possibilities of the determination by radioactivity measurements of³H,¹⁴C and¹³¹I are described for the individual nuclides and their mixtures, with the use of liquid scintillators. The changes in the counting efficiency have been determined as a function of the parameters of the measuring equipment, and parameters are suggested which make possible the determination of³H,¹⁴C and¹³¹I individually, or in the pairs³H−¹⁴C,³H−¹³¹I,¹⁴C−¹³¹I, and finally, in the triplet³H−¹⁴C−¹³¹I.     

Separation of131I by isotopic and non-isotopic liquid ion exchange

A study is presented on the use of isotopic and non-isotopic ion exchange in a heterogeneous liquid-liquid system for the separation of¹³¹I from water. The method is based on the reaction between radioiodide in the aqueous phase and trioctylmethylammonium iodide or chloride in the organic phase. The effect of some important experimental parameters on the separation efficiency is discussed. It has been found that under optimum conditions the method of isotopic ion exchange can be used for the radiochemical determination of iodine in water.     

Radiochemical separation of110mAg,210Pb,127Te and131I from aqueous nitric acid solution by bis-2-(butoxyethyl ether)

A bis-2-(butoxyethyl ether) (DBC) solvent extraction method has been developed for the radiochemical separation of^110mAg,²¹⁰Pb,¹²⁷Te and¹³¹I in varying concentrations of aqueous HNO₃. Various factors were examined to determine the optimum conditions of extraction. The effect of various masking agents has been studied. The extraction of¹³¹I is enhanced to 99% at 2.4M HNO₃ in the presence of KSCN.¹³¹I was stripped into aqueous sodium hydroxide from the oxygenated organic extractant. The method was then applied for the recovery of¹³¹I from neutron irradiated tellurium metal. The mechanism and reactivity of DBC with metal ions is described.     

A novel method for the simultaneous determination of125I and14C activities using liquid scintillation counting

The viability of a dual label liquid scintillation technique has been investigated. To avoid the need for two procedures, gamma counting for¹²⁵Iodine (¹²⁵I) and liquid scintillation counting for¹⁴C. Since the¹²⁵I spectrum covers almost as wide a range of pulse heights as¹⁴C, conventional dual label methods would result in very low¹⁴C counting efficiencies. The conventional dual label technique has ben modified to increase the¹⁴C counting efficiency and to accomodate the consequent additional spillover of¹²⁵I counts into the upper window. This dual label technique has been applied to the determination of¹²⁵I and¹⁴C activities in blood samples. The accuracy of the method has been tested, and its advantages and limitations are discussed.     

Radiometric determination of anionic surfactants by two-phase titration method with the use of131I-Rose Bengal as indicator

The paper describes a radiometric variant of the two-phase titration method for the determination of anionic surfactants of nonsoapy type. The method is based on the titration of an anionic surfactant with Septonex in alkaline medium in the presence of¹³¹I-Rose Bengal /abbreviated¹³¹I-RB/. The ion associates are extracted into chloroform. The equivalence point is determined graphically from the activity of¹³¹I-RB-Septonex associate, which is formed after the consumption of the anionic surfactant and which passes into the organic phase. The influence of¹³¹I-RB amount, pH of the titrated medium and of soap presence on the precision of anionic surfactants determination was studied. The detection limit is 2.88 g sodium n-dodecylsulphate in 10 ml of sample.     

Simultaneous determination of60Co,131I and137Cs in model radioactive waste water by reverse radiometric flow injection analysis with the aid of a multichannel analyzer

Reverse radiometric flow injection analysis was used for the simultaneous determination of⁶⁰Co,¹³¹I and¹³⁷Cs in model radioactive waste water. A NaI (Tl) scintillation detector coupled to a Canberra MCA was used for measuring the activity of¹³⁷Cs at 662 keV,⁶⁰Co at 1173 keV and 1332 keV, and¹³¹I at 364 keV.     

Simultaneous liquid scintillation determination of239Pu and241Am in tissue

A liquid scintillation counting method for the simultaneous determination of Pu and Am, with a two-phase cocktail, has been applied to the analysis of a tissue sample from an accidental exposure incident. The sample contained²³⁹Pu,²⁴¹Pu, and²⁴¹Am. In addition to analysis by two liquid scintillation counting techniques, analysis of the sample was performed by -spectroscopy and ZnS scintillation techniques, and the results were compared. The presence of²⁴¹Pu interfered with the liquid scintillation determination of²⁴¹Am when the two-phase cocktail was used, but the results were in agreement sufficient to be useful in determining what course of treatment, if any, might be necessary for the patient.     

New method for90Sr determination in liquid samples

A method has been developed for measuring⁹⁰Sr activity in liquid samples. After concentrating strontium from the sample by coprecipitation with calcium phosphate, the residue is dissolved in 8N HNO₃ and passed through an extraction chromatographic column (Sr.Spec) containing a new material that selectively retains strontium. This is eluted from the column with 0.05N HNO₃ and counted by liquid scintillation. Measurement is performed using a double window method, that allows a rapid and single determination of⁹⁰Sr.     

Separation and preconcentration of131I− and131IO 3 − in a liquid-liquid system

The application of isotope exchange in a liquid-liquid system for the separation and preconcentration of¹³¹I^– and¹³¹IO^3/– from water is described. For this purpose a solution of elemental iodine in tri-n-butyl phosphate diluted with toluene was used. The influence of various factors on the separation efficiency of¹³¹I was investigated. These are: time of the exchange, concentration of a carrier in the aqueous phase, concentration of I₂ in the organic phase, volume ratio of the phases, pH, foreign ions, storage of the organic phase, etc. The method is quite rapid and the selective preconcentration of these chemical forms of radioiodine from water can be accomplished even in the presence of the most important fission products. This method makes also possible to separate these chemical forms from each other under controlled pH conditions. The activity of the separated radioiodine can be measured advantageously, e.g., by homogeneous liquid scintillation counting after decolourization of the organic phase.     

An extraction method for the determination of the Rose Bengal content in the preparations of Rose Bengal labelled with131I

The paper describes an extraction radiometric method for the determination of Rose Bengal content in the radiopharmaceutical preparations of Rose Bengal labelled with¹³¹I. Two methods have been studied. The first one is based on the addition of an excess and substoichiometric amounts of Septonex /carbetoxypentadecyltrimethylammonium bromide/ to the sample of Rose Bengal-¹³¹I and on the activity measuring of the chloroform extracts. The second method is based on the extraction of Rose Bengal-¹³¹I with substoichiometric amount of Septonex from the sample of Rose Bengal-¹³¹I and the sample of Rose Bengal-¹³¹I diluted with a known amount of an inactive Rose Bengal preparation.     

Quantification of99Tc by liquid scintillation counting: An evaluation of chemical quenching by liquid chromatographic eluents

The feasibility of utilizing liquid scintillation counting as a detection method for the liquid chromatographic analysis of⁹⁹Tc is evaluated. The chemical quenching of constituents commonly found in liquid chromatographic mobile phases is investigated, and quench corrections are presented. Quantification of⁹⁹Tc is achieved over a concentration range of 10^–3 to 10^–8M on quiescent KTCO₄ solutions, with sample volumes of 0.3 ml, yielding a counting efficiency from 51 to 59% for a narrow 150 channel window. The potential for the double isotope labelling of technetium complexes and the implications of the liquid scintillation counting of⁹⁹Tc in flowing eluents are discussed.     

Contribution of nuclear medicine procedures to global129I inventory

¹²⁹I content of batches of Na¹³¹I vials, used for nuclear medicine procedures, was estimated by neutron activation analysis. The average value of the¹²⁹I/¹³¹I activity ratio /corresponding to zero decay time of the latter/ was /4.98±2.8/x10^–9. It is concluded that the contribution of¹²⁹I from medical applications of¹³¹I in India is insignificant in relation to that from nuclear fuel cycle activities.     

Temperature dependence of pulse-height distribution in liquid scintillator

The differential pulse-height distributions for²⁴¹Am,^131mXe,¹⁴C and³H are investigated as a function of temperature. The spectra are shifted toward higher pulseheights with decreasing temperature. During the measurement, the temperature of photomultipliers of liquid scintillation system are kept at 8.8 °C. The counting efficiency of¹⁴C and³H increases with decreasing temperature. The mechanism involved in this effect is discussed.     

Determination of129I and127I in environmental samples by neutron activation analysis (NAA) and inductively coupled plasma mass spectrometry (ICP-MS)

In order to assess the levels and behavior of¹²⁹I (half-life: 1.6×10⁷ y) and¹²⁷I (stable) in the environment, we have developed analytical procedures involving neutron activation analysis (NAA). Environmental samples collected around Tokaimura, Ibaraki Prefecture, Japan, have been analyzed using this method. Ranges of¹²⁹I and¹²⁷I concentrations in surface soil were 0.9–180 mBq kg^–1 and 1–60 mg kg^–1, respectively. Higher¹²⁹I concentrations were found in soil samples collected from coniferous forests, suggesting a contribution from tree canopies in the deposition of this nuclide. Most of the¹²⁹I in soil, was found to be retained in the first 10 cm. The¹²⁹I/¹²⁷I ratios in wheat fields were lower than those in rice paddy fields.A soil sample collected by IAEA from an area contaminated by the Chemobyl accident was also determined. The¹²⁹I concentration and the¹²⁹I/¹²⁷I ratio were 1.6 mBq kg^–1 and 1.7×10^–7, respectively. The¹²⁹I level in this sample was higher than the values obtained in areas far from nuclear facilities in Japan. It was suggested that the analysis of¹²⁹I in soils in the Chernobyl area may be useful in evaluating the¹³¹I levels at the time of the accident.Analyses of¹²⁹I and¹²⁷I by ICP-MS in water samples were also made. The analytical speed of this method was very high, i.e., 3 minutes for a sample. However, there is a sensitivity limitation for¹²⁹I detection due to interference from¹²⁹Xe with the¹²⁹I peak. The detection limits for¹²⁹I and¹²⁷I in water samples were about 0.5 mBq ml^–1 and 0.1 ng ml^–1, respectively.     

Determination of <Superscript>129</Superscript>I using volatilization method and liquid scintillation spectrometry

A simple and rapid separation method for ¹²⁹I determination in radioactive waste samples was developed. Suitable conditions for iodine volatilization were tested. Iodine was trapped in 1.5 mol L^?1 NaOH and precipitated as PdI₂·H₂O by addition of PdCl₂ with recoveries higher than 80%. The method was applied for analysis of contaminated soil, radioactive sludge, evaporator concentrate and heterogeneous waste samples from nuclear power plants in Slovak Republic. ¹²⁹I was measured on liquid scintillation counter TRI CARB 2900 TR using Ultima Gold AB scintillation cocktail.     

Determination of iodine-129 and iodine-127 in environmental samples collected in Japan

Analytical method for the determination of¹²⁹I and¹²⁷I in environmental samples has been developed by using radiochemical neutron activation analysis. The¹²⁹I levels in the samples such as soil (0.9–41 mBq/kg), precipitation (0.002–0.11 mBq/kg), pine needles (1.2–32 mBq/kg) and seaweed (<0.1–17 mBq/kg) collected near the nuclear facilities in Tokaimura were higher than those from the other areas in Japan. The highest¹²⁹I concentration was found in surface soil (0–5 cm), and the highest¹²⁹I/¹²⁷I ratios were found in pine needles and precipitation. The¹²⁹I/¹²⁷I ratio was higher in rice paddy soil than those in wheat field soil collected around Tokaimura, while the concentration of¹²⁹I somewhat higher in wheat field soil.     

Separation of iodine produced from fission with a porous metal silver column in99Mo production

In Argentina, at the Ezeiza Atomic Center,¹³¹I is produced by wet distillation of natural tellurium dioxide irradiated with thermal neutrons in a pool-type reactor. In order to recover the¹³¹I present in the production process of fission⁹⁹Mo obtained by irradiation of UAL_x/Al targets (with 90% enriched uranium) a separation method was developed. Iodine isotopes can be separated from a sodium hydroxide solution containing fission products using a column filled with alternate beds of glass microspheres and porous metal silver. Tests with tracers were performed in radiochemical laboratory. Following this results, a series of tests with higher activities (3 TBq of⁹⁹Mo and 0.7 TBq of¹³¹I) were carried out in hot cells. Molybdenum passes through the silver column, while¹³¹I retention was 92–97% in tracer test and 90% in optimised hot cell tests. This result depends on several facts that are discussed. An initial separation of iodine isotopes diminishes radiation damage on ion-exchange resin used in the subsequent molybdenum purification, improving its retention and elution yield.     

Simultaneous determination of35S and14C in double-labelled organic compounds by liquid scintillation counting

An isotope analytical method for the simultaneous determination of³⁵S and¹⁴C in double-labelled organic compounds by liquid scintillation counting is described. The sample is burned in a stream of oxygen. Sulfur oxides are converted to sulfuric acid and separated from other combustion products, including carbon-14 dioxide, on a heated quartz wool column previously wetted with hydrogen peroxide. Carbon dioxide is collected from the gas stream by an absorbent suitable for liquid scintillation counting. The residual sulfuric acid is rinsed off the column with water and the aqueous solution obtained is mixed with a liquid scintillation cocktail for radioactivity measurement. The final solutions ready for counting are obtained in less than fifteen minutes, quantitative collection recovery is achieved and no cross contamination occurs.     

Aerosol and gaseous radioidine concentration in the air of Prague after the Chernobyl accident

Data on¹³¹I concentration in the atmosphere of Prague observed during the first days after the Chernobyl accident are presented. The sampling device enabling the differentiation between aerosol-fixed and gaseous form of¹³¹I is briefly described. The highest total¹³¹I concentration, 63 Bq.m^–3, was observed between 30 April and 1 May. Until 9 May the level of¹³¹I activity ranged between 14 and 1 Bq.m^–3 and then dropped below 1 Bq.m^–3. The content of gaseous¹³¹I was found to be a significant and represented on average 60–80% of its total activity.