Radiotracer application for characterization of nuclear grade anion exchange resins Tulsion A-23 and Dowex SBR LC
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P. U. Singare
Abstract
Radio isotopic tracer technique as one of the versatile nondestructive technique is employed to evaluate the performance of nuclear grade anion exchange resins Tulsion A-23 and Dowex SBR LC. The evaluation was made on the basis of ion-isotopic exchange reaction kinetics by using 131I and 82Br radioactive tracer isotopes. It was observed that for both the resins, the values of specific reaction rate (min−1), amount of ion exchanged (mmol) and initial rate of ion exchange (mmol/min) were calculated to be lower for bromide ion-isotopic exchange reaction than that for iodide ion-isotopic exchange reaction. It was observed that for iodide ion-isotopic exchange reaction under identical experimental conditions of 30.0 °C, 1.000 g of ion exchange resins and 0.001 mol/L labeled iodide ion solution, the values of specific reaction rate (min−1), amount of iodide ion exchanged (mmol), initial rate of iodide ion exchange (mmol/min) and log Kd were calculated as 0.377, 0.212, 0.080 and 15.5 respectively for Dowex SBR LC resin, which was higher than 0.215, 0.144, 0.031 and 14.1 respectively as that obtained for Tulsion A23 resins. Also at a constant temperature of 30.0 °C, as the concentration of labeled iodide ion solution increases from 0.001 mol/L to 0.004 mol/L, the percentage of iodide ions exchanged increases from 84.75 % to 90.20 % for Dowex SBR LC resins which was higher than increases from 57.66 % to 62.38 % obtained for Tulsion A23 resins. The identical trend was observed for the two resins during bromide ion-isotopic exchange reaction. The overall results indicate superior performance of Dowex SBR LC over Tulsion A23 resins under identical experimental conditions.
Kurzfassung
Ein zerstörungsfreies Verfahren mit radioaktiven Tracern wird verwendet zur Bewertung der Leistungsfähigkeit der hoch-reinen Ionenaustauschharze Tulsion A-23 und Dowex SBR LC. Die Bewertung erfolgte auf der Basis von Ionenaustausch-Reaktionen bei 131I und 82Br radioaktiven Tracern. Für beide Harze waren die berechneten Werte der spezifischen Reaktionsraten (min−1), der Anteil der ausgetauschten Ionen (mmol) und die Anfangsrate des Ionenaustauschs (mmol/min) niedriger bei Bromid-Ionenaustausch-Reaktionen als bei Iodid-Ionenaustausch-Reaktionen. Für Iodid-Ionenaustausch-Reaktionen lagen unter identischen experimentellen Bedingungen von 30.0 °C, 1.000 g Ionenaustauschharz und 0.001 mol/L markierte Iodid Ionenlösung, die Werte der spezifischen Reaktionsraten (min−1), der Anteil der ausgetauschten Iodid-Ionen (mmol), die Anfangsrate des Iodid-Ionenaustauschs (mmol/min) und log Kd bei 0.377, 0.212, 0.080 und 15.5. Für Dowex SBR LC Harz lagen die Werte mit 0.215, 0.144, 0.031 und 14.1 höher als bei Tulsion A23 Harz. Bei einer konstanten Temperatur von 30.0 °C, bei der sich die Konzentration der markierten Iodid-Ionen von 0.001 mol/L auf 0.004 mol/L erhöht, erhöhte sich der Anteil ausgetauschter Iodid-Ionen von 84.75 % auf 90.20 % für Dowex SBR LC Harz, ein Wert, der höher lag als der Anstieg von 57.66 % auf 62.38 %, der für Tulsion A23 Harz erhalten wurde. Der gleiche Trend wurde beobachtet für die beiden Harze während der Bromid-Ionenaustausch-Reaktion. Die Gesamtergebnisse zeigen eine bessere Leistungsfähigkeit von Dowex SBR LC Harz gegenüber Tulsion A23 Harz unter identischen experimentellen Bedingungen.
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© 2015, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Considering the uncertainties in empirical correlations for vertical countercurrent flow limitation (CCFL) with TRACE
- 3RIP trip startup test simulation of TRACE/PARCS model for Lungmen ABWR under different power and flow conditions
- Development of a new analytic function expansion nodal code, HexDANM, for solving the neutron diffusion equation in hexagonal-Z geometry
- Laser cleaning of steam generator tubing based on acoustic emission technology
- Axial enrichment profile in advance nuclear energy power plant at supercritical-pressures
- Analysis of the small break loss of coolant accident in the VVER-1000/V446 reactor
- Thermal hydraulic analysis of reactivity accidents in MTR research reactors using RELAP5
- Depletion of Gadolinium burnable poison in a PWR assembly with high burnup fuel
- Nuclear model calculations on cyclotron production of 51Cr
- Radiotracer application for characterization of nuclear grade anion exchange resins Tulsion A-23 and Dowex SBR LC
- Solving the criticality problem with the reflected boundary condition for the triplet anisotropic scattering with the modified FN method
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Considering the uncertainties in empirical correlations for vertical countercurrent flow limitation (CCFL) with TRACE
- 3RIP trip startup test simulation of TRACE/PARCS model for Lungmen ABWR under different power and flow conditions
- Development of a new analytic function expansion nodal code, HexDANM, for solving the neutron diffusion equation in hexagonal-Z geometry
- Laser cleaning of steam generator tubing based on acoustic emission technology
- Axial enrichment profile in advance nuclear energy power plant at supercritical-pressures
- Analysis of the small break loss of coolant accident in the VVER-1000/V446 reactor
- Thermal hydraulic analysis of reactivity accidents in MTR research reactors using RELAP5
- Depletion of Gadolinium burnable poison in a PWR assembly with high burnup fuel
- Nuclear model calculations on cyclotron production of 51Cr
- Radiotracer application for characterization of nuclear grade anion exchange resins Tulsion A-23 and Dowex SBR LC
- Solving the criticality problem with the reflected boundary condition for the triplet anisotropic scattering with the modified FN method
