Title: Dynamic leaching studies of 48 MWd/kgU UO2 commercial spent nuclear fuel under oxic conditions
Authors: SERRANO PURROY DanielCASAS I.GONZALES-ROBLES ErnestoGLATZ Jean-PaulWEGEN DetlefCLARENS FedericGIMENEZ J.DE PABLO J.MARTINEZ-ESPARZA A.
Citation: JOURNAL OF NUCLEAR MATERIALS vol. 434 no. 1-3 p. 451-460
Publisher: ELSEVIER SCIENCE BV
Publication Year: 2013
JRC N°: JRC64308
ISSN: 0022-3115
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC64308
DOI: 10.1016/j.jnucmat.2011.03.020
Type: Articles in periodicals and books
Abstract: The leaching of a high-burn-up spent nuclear fuel (48 GWd/tU) 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 with 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. Keywords: spent nuclear fuel, dynamic leaching, Instant release fraction PACS Codes: 89.30.Gg, 28.41.Bm, 28.41.Kw, 82.60.Hc
JRC Directorate:Nuclear Safety and Security

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