Ľubomír Mátel

Extraction of strontium using an irradiated extraction agent of crown structure

The partition coefficient of strontium upon its extraction from the aqueous solutions of picric acid into chloroform containing DC-18-crown-6, B-15-crown-5 after their exposition to gamma radiation has been studied. A significant decrease of the partition coefficient in the studied range of doses 10–70 kGy was observed. This effect can be attributed to the radiolytic products of chloroform. The radiation destruction as well as dehydrogenation of crown ethers were not observed.

Determination of 93 Zr in radioactive waste using ion exchange techniques

This paper describes a simple and rapid method of 93Zr pre-concentration, separation and purification by using cation and anion exchange resins which are commercially available from Eichrom Technologies, Inc.,. The method is suitable for analyzing high contaminated radioactive waste samples in a relatively short time and high decontamination factors. The use and effectiveness of this method was successfully tested by analysis of heterogeneous waste from nuclear power plant and samples from nuclear reactor and fuel parts such as control rod drive shaft and neutron absorbers, shielding cassettes and neutron in-core measurement channels (KNI) samples.

Determination of 94Nb in radioactive waste using ion exchange chromatography

This paper describes a rapid method of 94Nb pre-concentration, separation and purification by using cation and anion exchange resins. The method is suitable for analyzing highly contaminated radioactive waste samples in a relatively short time and high decontamination factors. The use and effectiveness of the method was successfully tested by analysis of samples from nuclear reactor parts such as control rod drive shaft, shielding cassettes, neutron in-core measurement channels (KNI), pressure vessel construction material and fuel cassette construction material samples.

Adsorption of alkali and alkaline earth radionuclides on zeolite from water solutions

The adsorption of cesium and strontium ions from water solutions on zeolite has been investigated in presence of sodium, potassium, magnesium and calcium ions. Distribution ratios of cesium and strontium on the zeolite were determined in solutions of various compositions and solution volume to sorbent weight ratios (batch factor). Breakthrough curves for zeolite layers are reported.

Development of a method for the determination of 93Zr and 94Nb in radioactive waste using TEVA® resin

The behaviour of 95Zr and 95Nb isotopes on TEVA® resin column was studied. The influence of hydrofluoric, hydrochloric, oxalic and sulphuric acids on the separation and chemical yield of zirconium and niobium was tested. The method is suitable for the separation of 93Zr and 94Nb isotopes from hydrofluoric, hydrochloric and sulphuric acid by using different concentrations of the acid for the load or elutes solutions. Samples from reactor and fuel assemblies such as the control-rod connection rod, shielding/absorber parts of fuel rods, neutron in-core measurement channels, pressure vessel basic construction material and internal cladding, core barrel and reactor protection tube unit were analysed.

Determination of239, 240Pu in environmental samples from surroundings of the atomic power station Jaslovske Bohunice

The development of a rapid and reproducible method for the separation of plutonium from soil samples is described. Tetravalent plutonium is extracted from 8M HNO3 into 30% Aliquat-336/toluene mixture. Uranium and thorium are removed with nitric and hydrochloric acid washes. Plutonium is backextracted with HCl−H2C2O4 and HCl−HF solutions. Plutonium is coprecipitated with NdF3 and filtrated onto a 0.1–0.2 μm membrane filter to prepare a source for α-spectrometry. The chemical yields of separation are about 50–60%.

Radiation-chemical changes of benzo-15-crown-5 in chloroform

NMR, IR and MS were used for identification of major products of radiolysis of benzo-15-crown-5 in chloroform. The crown ether exhibits high affinity towards inorganic products of radiolysis of chloroform resulting in the formation of complexes.

Determination of alpha, beta, X-ray and gamma emitting radionuclides in reactor components and fuel assemblies from NPP V1 Jaslovske Bohunice

The radionuclides in reactor and fuel construction parts of the V1 Jaslovske Bohunice nuclear power plant (NPP V1) were identified and their activity was measured. Samples from reactor and fuel assemblies such as control rod connection rod, shielding/absorber parts of fuel rod, neutron in-core measurement channels, pressure vessel basic construction material and internal cladding, core barrel and protective tube unit were analyzed. Activity concentrations of 60Co, 55Fe, 63,59Ni, 90Sr, 99Tc, 93Mo, 94Nb, transuranic elements were determined. Analytical and sampling methods are briefly described for the measured radionuclides. The presented results were used for characterization of the waste during the decommissioning of NPP V1 nuclear reactors.

Determination of 99Tc in soil samples using molecular recognition technology product AnaLig® Tc-02 gel

The purpose of this study was to test a method for 99Tc determination in soil samples from locality Bratislava Podunajske Biskupice by using solid phase extraction technique with a new sorbent AnaLig® Tc-02—molecular recognition technology product. The method is suitable for analyzing soil samples in a relatively short time and high recoveries. The use and effectiveness of AnaLig® Tc-02 were successfully tested by analysis of soil and spiked soil samples.

Determination of 239,240Pu, 238Pu isotopes in soil samples using molecular recognition technology product AnaLig®Pu-02 gel

Procedure for analysis of plutonium isotopes in soil samples was developed using a new molecular recognition technology product AnaLig®Pu-02 gel. Extraction chromatography TEVA® Resin was used for purification of plutonium phase to remove thorium impurities which interfere in Pu determination by alpha spectrometry. The performance of the method was successfully tested by analysis of a sand stimulant sample and a soil sample spiked with known activity of 239Pu. The results obtained for procedures were compared in terms of activities and recoveries.