Title: Leaching of 53MW/d kgU Spent Nuclear Fuel in a Flow-through Reactor
Authors: SERRANO PURROY DanielCLARENS FedericGLATZ Jean-PaulWEGEN DetlefCHRISTIANSEN BirgitDE PABLO J.GIMENEZ J.CASAS I.MARTINEZ-ESPARZA A.
Citation: RADIOCHIMICA ACTA vol. 97 p. 491-496
Publisher: OLDENBOURG VERLAG
Publication Year: 2009
JRC Publication N°: JRC56815
ISSN: 0033-8230
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC56815
DOI: 10.1524/ract.2009.1640
Type: Articles in Journals
Abstract: The dissolution behaviour of powdered commercial spent fuel (UO2 with burn-up of 53MW/d kgU) has been studied in a carbonate-containing solution ([HCO3-] = 0.001 mol dm-3) by using a flow-through reactor specially designed for the use in a hot cell. This method allows studying spent fuel dissolution while avoiding the parallel process of secondary solid phase formation. The dissolution behaviour of U, Np, Pu, Sr and Cs was studied. The main trend of the results obtained in this work is that only neptunium releases congruently with uranium (FIAPNp/FIAPU = 1.21±0.01) because both strontium and caesium have higher FIAP values (FIAPSr/FIAPU = 2.3±0.8; FIAPCs/FIAPU = 5±1) and plutonium lower (FIAPPu/FIAPU = 0.07±0.02). The FIAP value for uranium at the steady-state is 4(±2) × 10-4.
JRC Institute:Institute for Transuranium Elements

Files in This Item:
There are no files associated with this item.


Items in repository are protected by copyright, with all rights reserved, unless otherwise indicated.