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contributor authorCastro, Hernán Ariel
contributor authorRodríguez, Raúl Ariel
contributor authorLuca, Vittorio
contributor authorBianchi, Hugo Luis
date accessioned2019-09-18T09:04:48Z
date available2019-09-18T09:04:48Z
date copyright3/15/2019 12:00:00 AM
date issued2019
identifier issn2332-8983
identifier otherners_005_02_020901.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4258609
description abstractTreatment and conditioning of spent ion exchange resins from nuclear facilities is a complex process that not only should contemplate obtaining a stable product suitable for long-term storage and/or disposal, but also have to take into account the treatment of secondary currents generated during the process. The combination of low temperature pyrolysis treatment and high performance plasma treatment (HPPT) of the off-gas generated could be a novel solution for organic matrix nuclear wastes with economic and safety advantages. In the present work, results of lab scale studies associated with the pyrolysis off-gas characterization and the performance and operating parameters influence on the removal of model compounds in a laboratory-scale flow reactor, using inductively coupled plasma under subatmospheric conditions, are shown. The pyrolysis off-gas stream was largely characterized and the evolution of main compounds of interest as function of temperature process was established. The results of plasma assays with the model compound demonstrate a high destruction and removal efficiency (>99.990%) and a good control over the final gas products. First results of a bench scale arrangement combining both processes are presented and bode well for the application of this combined technology.
publisherAmerican Society of Mechanical Engineers (ASME)
titlePyrolysis and High Performance Plasma Treatment Applied to Spent Ion Exchange Resins
typeJournal Paper
journal volume5
journal issue2
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4042193
journal fristpage20901
journal lastpage020901-8
treeJournal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 002
contenttypeFulltext


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