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  • 1
    Electronic Resource
    Electronic Resource
    Automated separation process for radioanalytical purposes at nuclear power plants
    Amsterdam : Elsevier
    Journal of Chromatography A 406 (1987), S. 359-366 
    Details
    ISSN: 0021-9673
    Source: Elsevier Journal Backfiles on ScienceDirect 1907 - 2002
    Topics: Chemistry and Pharmacology
    Type of Medium: Electronic Resource
    URL: http://linkinghub.elsevier.com/retrieve/pii/S0021-9673(00)94043-3
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  • 2
    Electronic Resource
    Electronic Resource
    Determination of radioactive bulk and surface concentration by beta-detection (1996)
    Springer
    Journal of radioanalytical and nuclear chemistry 209 (1996), S. 27-39 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract A method for determining bulk or surface activity concentration of β-emitters in “infinitely” thick or thin samples using energy selective detectors without any prior chemical separation or qualitative analysis was introduced in Part I. In addition to that method, a correction procedure is often required in order to compensate for the γ-sensitivity of the β-detector. A system or two — preferably identical —detectors positioned to the front and rear side of a sample has been established. The rear side detector is shielded against β-radiation. The γ-response of both detectors is determined as a function of γ-energy using monoenergetic calibration standards. Response pulses are selected to form 8 or 16 energy intervals, and separate series of correction coefficients are then computed for each interval and standard energy using the ratio of the respective counts. When a sample having mixed β- and γ-radiation is evaluated, an “effective” γ-energy is first calculated from the pulse height distribution of the rear side detector, the appropriate series of correction coefficients is selected and finally net β-counts are generated from the counts of the front side detector. Sensitivities in natural and elevated γ-background are presented.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02063529
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  • 3
    Electronic Resource
    Electronic Resource
    Method for investigation of various iodine species in the primary coolant of the Nuclear Power Plant in Paks (1996)
    Springer
    Journal of radioanalytical and nuclear chemistry 211 (1996), S. 453-460 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract Iodine isotopes formed in the course of fission in nuclear reactors may be present in the primary coolant in different oxidation states, i.e., in different chemical forms. It is important to know the chemical forms and their proportions in order to asses the environmental effect of the emitted iodine and the performance of air filters used in the primary circuit for binding iodine species, since both depend on the chemical forms in which it is present. Volatile components were separated from water samples taken separately from each block of the nuclear power station by purging with inert gas, then the aerosol, iodine vapour and alkyl iodides were selectively bound on the filter system of the “KOMBI” sampler. I 3 − , I−, IO−, IO 3 − and IO 4 − left in the aqueous phase after purging were separated by consecutive physical and chemical procedures (extraction, isotope exchange, reduction). The results of the investigations have shown that the water technology used in the Nuclear Power Plant in Paks is appropriate with respect to the radioiodine balance. Iodine was found to be the predominant species, and no volatile iodine species were found to be present in the primary coolant. Volatile iodine species sometimes appearing in emissions may be formed from leaching waters due to secondary effects.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02039711
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  • 4
    Electronic Resource
    Electronic Resource
    Dosimetric measurement of the disintegration rate of fission products (1992)
    Springer
    Journal of radioanalytical and nuclear chemistry 162 (1992), S. 187-198 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract Investigations on the disintegration rate of fission products of238U and239Pu are presented. The intensity of the β- and γ-radiation of fission products were measured continuously in an interval of 1–1300 hours following the fission, offering the possibility for determining the general and specific characteristics of the individual fission products. A universal measuring procedure was elaborated for the rapid in situ determination of the dosimetric features of fission products, which is suitable for the accurate evaluation and prediction of external absorbed dose even in case of fission products of various origin and unknown composition.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02039940
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  • 5
    Electronic Resource
    Electronic Resource
    Application of radioisotope-excited X-ray fluorescence to the determination of trace elements in blood (1992)
    Springer
    Journal of radioanalytical and nuclear chemistry 164 (1992), S. 275-283 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract A radioisotope-excited energy-dispersive X-ray fluorescence system has been constructed and used for the analysis of blood samples for trace elements. The possibility of determination of trace elements in blood by X-ray fluorescence based on comparison with standard reference materials has been outlined and the applicability of the method demonstrated by the analysis of blood samples. The method enables fast, non-destructive direct analyses to be carried out without lengthy sample pretreatment on a routine basis.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02165283
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  • 6
    Electronic Resource
    Electronic Resource
    A procedure for the continuous control of the retention properties of gas adsorber systems (1997)
    Springer
    Journal of radioanalytical and nuclear chemistry 218 (1997), S. 81-85 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract The retention of the radioactive noble gases takes place on the charcoal adsorber by dynamic adsorption, meanwhile their radioactivity decrease according to their half-life-times. For the optimal operation of the adsorber units the on-line control and analysis of the retention properties would be required. Therefore a procedure has been developed for the determination of the retention times and the dynamic adsorption coefficients for the specific noble gas isotopes. The method is based on the continuous analysis of the in- and out-flow of the adsorber system by γ-ray spectroscopy using semiconductor detectors. After the successful laboratory test, the procedure was installed and the retention properties of a charcoal based radioactive gas adsorber system were determined. For the evaluation of the data, a theoretical model was developed, which was used for the calculation of the dynamic retention coefficients of the noble gas isotopes.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02033978
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  • 7
    Electronic Resource
    Electronic Resource
    Determination of transuranium elements in nuclear power plant wastes (1996)
    Springer
    Journal of radioanalytical and nuclear chemistry 203 (1996), S. 135-141 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02060388
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  • 8
    Electronic Resource
    Electronic Resource
    Determination of radioactive bulk and surface concentration by beta-detection (1996)
    Springer
    Journal of radioanalytical and nuclear chemistry 209 (1996), S. 15-26 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract A quantitative method for the analysis of β-emitters in “infinitely” thin and thick samples was described in Part I. The calculation of errors in intensity, intensity ratio and activity concentration is discussed here in detail. Different definitions of detection sensitivity are compared and evaluated on the basis of the relative statistical error associated therewith. Dependence between the relative error of the net signal and the required measurement time is deduced and illustrated.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02063528
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  • 9
    Electronic Resource
    Electronic Resource
    Determination of radioactive bulk and surface concentration by beta-detection (1996)
    Springer
    Journal of radioanalytical and nuclear chemistry 209 (1996), S. 3-14 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract The activity concentration of bulk and surface samples contaminated with β-emitting radioisotopes is difficult to measure without the “a priori” knowledge of the nature of the non-gamma emitting components. Beta-emitters cannot be identified from any measured spectral distribution. The counting efficiency of the measuring system changes significantly with β-energy so it cannot be assumed to have a single value obtained with a standard source with known energy. Application of an energy selective β-detector is introduced for determining bulk and surface activity concentration. Samples of “infinitely thick” or “infinitelythin” nature are to be prepared. The distribution of β-energy deposited in the detector is registered as counts in 8 or 16 energy intervals. No information is needed on the qualitative composition of the sample. Normalised integral distributions (intensity ratios) are derived from the count rates of the intervals. These distributions are then compared to calibrated intensity ratios obtained with suitable standard sources. An average (effective) counting efficiency is generated from this comparison by a special algorithm. Activity concentration of an unknown sample is then obtained using this average efficiency. Calibration and sensitivity data are presented for different types of bulk and surface samples.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02063527
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  • 10
    Electronic Resource
    Electronic Resource
    Inventory determination of low and intermediate level radioactive waste of Paks Nuclear Power Plant origin (1996)
    Springer
    Journal of radioanalytical and nuclear chemistry 211 (1996), S. 443-451 
    Details
    ISSN: 1588-2780
    Source: Springer Online Journal Archives 1860-2000
    Topics: Chemistry and Pharmacology , Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract In the execution of disposal of low and intermediate level radioactive wastes, it is important to evaluate accurately the kind and quantity of each radionuclide in the wastes. For such an evaluation, correlation of non-gamma-emitting nuclides based on gamma-emitting nuclides is recommended and regarded as a practical method. This method necessitates a completion of a highly accurate and reliable nondestructive assay system of gamma-emitting nuclides for practical use. In 1992, in support of the new waste disposal program in Hungary, Paks NPP initiated a waste characterization program to determine the radiological properties of its radwastes. A segmented gamma scanning system has been set up to measure the gamma-emitting nuclides in 200 litre low level drums following in-drum compaction. In the framework of the program a radiochemical analysis sub-program was started to determine the long-lived non-gamma emitting radionuclides, mainly those listed in the US regulatory document (10CFR61). The radionuclides of interest have been3H,14C,90Sr,55Fe,59Ni,99Tc,129I and TRUs. Sample preparation techniques and measurement methods have been selected and used. Newly developed or adopted methods have been tested on real liquid radwaste streams such as concentrates, ion-exchange resin and sludge. The measurements taken so far have revealed brand new information and data on radiological composition of waste of WWER-type reactors. In the next stage of the characterisation program attempt will be made for providing correlation factors between the gamma and non-gamma-emitting radionuclides in different waste streams. Short description of the methods and results on waste inventory are given by highlighting the problem areas.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1007/BF02039710
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