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  • Author or Editor: Silvia Dulanská x
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Abstract  

The decommissioning of the nuclear power plant (NPP) A1 Jaslovské Bohunice (Slovakia) is a complicated set of problems that is highly demanding both technically and financially. The basic goal of the decommissioning process is the total elimination of radioactive materials from the nuclear power plant area, and radwaste treatment to a form suitable for its safe disposal. The initial conditions of decommissioning also include elimination of the operational events, preparation and transport of the fuel from the plant territory, radiochemical and physical–chemical characterization of the radioactive wastes. One of the problems was and still is the processing of the liquid radioactive wastes. Such media is also the cooling water of the long-term storage of spent fuel. A suitable scaling model for predicting the activity of hard-to-detect radionuclides 239,240Pu, 90Sr and summary beta in cooling water using a regression triplet technique has been built using the regression triplet analysis and regression diagnostics.

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Abstract  

A rapid separation method has been developed which allows measurement of plutonium, americium and strontium isotopes in the radioactive sludge from Nuclear power plant A1 Jaslovske Bohunice (NPP A1) with high chemical recoveries and effective removal of matrix interferences. This method uses different commercial products stacked AnaLig® Pu02, AnaLig® Sr01 and TRU® Resin cartridges from IBC Advanced Technologies and Eichrom Technologies. The method allows the rapid separation of plutonium, strontium and americium using a single multi-stage column in the vacuum box (cartridge technology) with rapid flow rates to minimize sample separation time. The 239,240Pu, 238Pu and 241Am were determined by alpha spectroscopy, 90Sr was counted on TRICARB 2900 TR by Cerenkov counting of its progeny 90Y.

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Abstract  

We studied the use of an extraction chromatography for determination of 90Sr in contaminated water samples. The aim of our work was to compare selected products from the point of view of the strontium chemical yields and analysis time. Three commercial products, 3M Empore™ Strontium Rad Disk, AnaLig® Sr-01 gel, Sr®Resin, and two classical methods, liquid–liquid extraction with tributhylphosphate and carbonate co-precipitation, were tested for the separation of 90Sr. The water sample from nuclear power plant A1 Jaslovske Bohunice was used for radiochemical analysis of 90Sr volume activity. Samples were traced with 85Sr to monitor strontium chemical recovery and counted either by Cerenkov counting on TRI CARB 2900 TR liquid scintillation counter or low level alpha–beta proportional counter.

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Abstract  

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.

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Abstract  

Two separation techniques for plutonium determination using AnaLig® Pu02 molecular recognition technology product (MRT) and extraction chromatography TRU® resin were tested. The methods performance was investigated by analysis of National Physical Laboratory (NPL-Alpha-Beta High, ABH 2003, 2005) intercomparison test samples. The results obtained for both procedures were compared in terms of activities and recoveries. Data analysis showed good agreement with the reference values. The AnaLig® Pu02 separation method for 239,240Pu, 238Pu determination was successfully validated with the same performance as the TRU® resin method.

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Abstract  

This paper describes the use of IBC′s AnaLig®Sr-01 molecular recognition technology product to effectively and selectively pre-concentrate, separate and recover strontium from radioactive waste samples. The use and effectiveness of AnaLig®Sr-01 gel was successfully validated by analysis of International Atomic Energy Agency (IAEA 375) reference soil and National Physical Laboratory (NPL)–High Alpha–Beta (2003) liquid sample. The second part of this paper focuses on analysis of radioactive waste samples from nuclear power plant A1 Jaslovske Bohunice in Slovak Republic (NPP A1).

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Abstract  

Two separation techniques for plutonium determination using IBCS AnaLig® Pu02 molecular recognition technology product (MRT) and extraction chromatography TRU® resin (Eichrom ®Industries) to effectively and selectively separate and recover plutonium were tested. The performance of the methods was successfully tested by analysis of NPL (High Alpha–Beta 2003, 2005) intercomparison sample and radioactive sludge sample from NPP A1 Jaslovské Bohunice with high activities of the plutonium radionuclides. The results obtained for both procedures were compared in terms of activities and recoveries.

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Abstract  

In this paper rapid separation methods for strontium determination using molecular recognition technology products 3M Empore™ Sr disc, AnaLig® Sr-01 and extraction chromatography Sr® Resin were presented and statistical tested. The methods performance was investigated by analysis of NPL (High Alpha–Beta 2003) and (High Alpha–Beta 2005) intercomparison samples. The presented results were evaluated as correct for all experimental data. We used linear regression (with regression diagnostics), t test and the mean of variable using 90Sr with 3M Empore™ Sr disc, AnaLig® Sr-01 and Sr® Resin.

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Abstract  

This paper describes a simple and rapid method of 99Tc pre-concentration, separation and purification by using AnaLig® Tc02 gel in two stages or AnaLig® Tc02 gel in a first stage and TEVA® resin in a second stage, which are commercially available from IBC advanced technologies, Inc. and Eichrom technologies, Inc., respectively. The method is suitable for analyzing large volume concentrate samples in a relatively short time. The use and effectiveness of AnaLig® Tc02 and Eichrom’s TEVA® resin were successfully tested by analysis of evaporator concentrate samples which belong to the class of most difficult matrices to analyze.

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Abstract  

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.

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