Nondestructive radioactive tracer technique in performance evaluation of organic based ion exchange materials Purolite NRW-4000 and Duolite A-378
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P. U. Singare
Abstract
The present paper demonstrates nondestructive application of the 131I and 82Br radioisotopes in performance evaluation of organic base anion exchange resins Purolite NRW-4000 and Duolite A-378. The evaluation was based on kinetics of iodide and bromide ion-isotopic exchange reactions taking place between the external ionic solution and the resin surface. It was observed that at a constant temperature of 35.0 °C when the concentration of bromide ions in solution increases from 0.001 mol/L to 0.004 mol/L, the specific reaction rate values for bromide ion-isotopic exchange increases from 0.228 to 0.266 min−1 using Purolite NRW-4000 resins and from 0.160 to 0.185 min−1 using Duolite A-378 resins. Also it was observed that under the same experimental conditions, the percentage of bromide ions exchanged increases from 60.67 % to 67.00 % using Purolite NRW-4000 resin, while for Duolite A-378 resin it increases from 49.30 % to 52.00%. The identical trend was observed for the two resins during iodide ion-isotopic exchange reaction. The overall results indicate that under identical experimental conditions, as compared to Duolite A-378 resins, Purolite NRW-4000 resins shows superior performance. It is expected that the present nondestructive radiotracer technique can be extended further for characterization of series of nuclear as well as non-nuclear grade ion exchange resins. The results of such study will be immensely useful in proper selection of the ion exchange resins in various industrial applications.
Kurzfassung
Der vorliegende Betrag zeigt die zerstörungsfreie Anwendung von 131I und 82Br bei der Bewertung der Leistungsfähigkeit der Ionenaustauschharze Purolite NRW-4000 and Duolite A-378. Die Bewertung basiert auf der Kinetik der Iodid- und Bromid-Ionenaustausch-Reaktionen zwischen der externen Ionenlösung und der Harzoberfläche. Es wurde beobachtet, dass bei einer konstanten Temperatur von 35.0 °C, wenn die Konzentration der Bromidionen in Lösung von 0.001 mol/L auf 0.004 mol/L ansteigt, die Werte der spezifischen Reaktionsraten für den Bromidionenaustausch von 0.228 auf 0.266 min−1 ansteigen bei Verwendung von Purolite NRW-4000 Harz und von 0.160 auf 0.185 min−;1 bei Verwendung von Duolite A-378 Harz. Unter den gleichen experimentellen Bedingungen wurde auch beobachtet, dass der Prozentsatz der ausgetauschten Bromidionen von 60.67 % auf 67.00 % ansteigt bei Verwendung von Purolite NRW-4000 Harz, bei Verwendung von Duolite A-378 Harz von 49.30 % auf 52.00 %. Der gleiche Trend wurde für die beiden Harze beobachtet während der Iodid-Ionenaustausch-Reaktion. Die Ergebnisse zeigen, dass unter identischen experimentellen Bedingungen Purolite NRW-4000 Harz eine bessere Leistungs-fähigkeit hat als Duolite A-378 Harz. Es wird davon ausgegangen, dass das derzeitige zerstörungsfreie Radiotracer-Verfahren erweitert werden kann zur Bestimmung der Eigenschaften von hoch-reinen Ionenaustauschharzen. Die Ergebnisse solcher Untersuchungen wären von großem Nutzen bei der Auswahl geeigneter Ionenaustauschharze für verschiedene industrielle Anwendungen.
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© 2015, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Improved data evaluation methodology for energy ranges with missing experimental data
- Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems
- Safety assessment of fuel cycle facilities following the lessons learned from the accident at the Fukushima-Daiichi nuclear power plant
- The ultimate response guideline simulation and analysis by using TRACE for Lungmen ABWR nuclear power plant
- Development of a hydrogen diffusion gothic model of MARK III-containment
- Analysis of safety parameters for the MINERVE reactor
- Nondestructive radioactive tracer technique in performance evaluation of organic based ion exchange materials Purolite NRW-4000 and Duolite A-378
- Neutronic performance of (ReprocessedU/Th)O2 fuel in CANDU 6 reactor
- Modelling study on production cross sections of 111In radioisotopes used in nuclear medicine
- Study of 60Co as gamma source in backscatter gamma densitometers
- Determination of activity concentration of natural and artificial radionuclides in sand samples from mediterranean coast of Antalya in Turkey
- Technical Notes
- Numerical solution of diffusion equation to study fast neutrons flux distribution for variant radii of nuclear fuel pin and moderator regions
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Improved data evaluation methodology for energy ranges with missing experimental data
- Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems
- Safety assessment of fuel cycle facilities following the lessons learned from the accident at the Fukushima-Daiichi nuclear power plant
- The ultimate response guideline simulation and analysis by using TRACE for Lungmen ABWR nuclear power plant
- Development of a hydrogen diffusion gothic model of MARK III-containment
- Analysis of safety parameters for the MINERVE reactor
- Nondestructive radioactive tracer technique in performance evaluation of organic based ion exchange materials Purolite NRW-4000 and Duolite A-378
- Neutronic performance of (ReprocessedU/Th)O2 fuel in CANDU 6 reactor
- Modelling study on production cross sections of 111In radioisotopes used in nuclear medicine
- Study of 60Co as gamma source in backscatter gamma densitometers
- Determination of activity concentration of natural and artificial radionuclides in sand samples from mediterranean coast of Antalya in Turkey
- Technical Notes
- Numerical solution of diffusion equation to study fast neutrons flux distribution for variant radii of nuclear fuel pin and moderator regions
