Dynamic leaching studies of 48 MWd/kgU UO2 commercial spent nuclear fuel under oxic conditions

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dc.contributor	Universitat Politècnica de Catalunya. Departament d'Enginyeria Química
dc.contributor	Universitat Politècnica de Catalunya. SETRI - Grup de Tècniques de Separació i Tractament de Residus Industrials
dc.contributor.author	Serrano Purroy, D.
dc.contributor.author	Casas Pons, Ignasi
dc.contributor.author	Gonzalez Robles, E.
dc.contributor.author	Glatz, Jean Paul
dc.contributor.author	Wegen, D.H.
dc.contributor.author	Clarens Blanco, Frederic
dc.contributor.author	Giménez Izquierdo, Francisco Javier
dc.contributor.author	Pablo Ribas, Joan de
dc.contributor.author	Martínez Esparza, A.
dc.date	2013-03
dc.identifier.citation	Serrano, D. [et al.]. Dynamic leaching studies of 48 MWd/kgU UO2 commercial spent nuclear fuel under oxic conditions. "Journal of nuclear materials", Març 2013, vol. 434, núm. 1-3, p. 451-460.
dc.identifier.citation	0022-3115
dc.identifier.citation	10.1016/j.jnucmat.2011.03.020
dc.identifier.uri	http://hdl.handle.net/2117/20861
dc.language.iso	eng
dc.relation	http://www.sciencedirect.com/science/article/pii/S0022311511002881
dc.rights	Attribution-NonCommercial-NoDerivs 3.0 Spain
dc.rights	info:eu-repo/semantics/openAccess
dc.rights	http://creativecommons.org/licenses/by-nc-nd/3.0/es/
dc.subject	Àrees temàtiques de la UPC::Enginyeria química::Química del medi ambient
dc.subject	Nuclear fuels
dc.subject	BURN-UP FUEL
dc.subject	OXIDIZING CONDITIONS
dc.subject	DISSOLUTION RATES
dc.subject	RIM REGION
dc.subject	CORROSION
dc.subject	RELEASE
dc.subject	MICROSTRUCTURE
dc.subject	GROUNDWATER
dc.subject	OXIDATION
dc.subject	DISPOSAL
dc.subject	Combustibles nuclears
dc.title	Dynamic leaching studies of 48 MWd/kgU UO2 commercial spent nuclear fuel under oxic conditions
dc.type	info:eu-repo/semantics/publishedVersion
dc.type	info:eu-repo/semantics/article
dc.description.abstract	The leaching of a high-burn-up spent nuclear fuel (48 MWd/KgU) has been studied in a carbonate-containing solution and under oxic conditions using a Continuously Stirred Tank Flow-Through Reactor (CSTR). Two samples of the fuel, one prepared from the centre of the pellet (labelled CORE) and another one from the fuel pellet periphery, enriched with the so-called High Burn-Up Structure (HBS, labelled OUT) have been used. For uranium and actinides, the results showed that U, Np, Am and Cm gave very similar normalized dissolution rates, while Pu showed slower dissolution rates for both samples. In addition, dissolution rates were consistently two to four times lower for OUT sample compared to CORE sample. Considering the fission products release the main results are that Y, Tc, La and Nd dissolved very similar to uranium; while Cs, Sr, Mo and Rb have up to 10 times higher dissolution rates. Rh, Ru and Zr seemed to have lower dissolution rates than uranium. The lowest dissolution rates were found for OUT sample. Three different contributions were detected on uranium release, modelled and attributed to oxidation layer, fines and matrix release.
dc.description.abstract	Peer Reviewed

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