Title: Corrosion of Irradiated MOX Fuel in Presence of Dissolved H2
Authors: CARBOL PaulFORS PatrickVAN WINCKEL StefaanSPAHIU K.
Citation: JOURNAL OF NUCLEAR MATERIALS vol. 392 no. 1 p. 45-54
Publisher: ELSEVIER SCIENCE BV
Publication Year: 2009
JRC N°: JRC52956
ISSN: 0022-3115
URI: http://www.sciencedirect.com/science?_ob=ArticleURL&_udi=B6TXN-4VXMPWR-1&_user=4692159&_coverDate=03%2F26%2F2009&_alid=897698084&_rdoc=1&_fmt=high&_orig=search&_cdi=5595&_sort=d&_docanchor=&view=c&_ct=1&_acct=C000036252&_version=1&_urlVersion=0&_userid=46
http://publications.jrc.ec.europa.eu/repository/handle/JRC52956
DOI: 10.1016/j.jnucmat.2009.03.044
Type: Articles in Journals
Abstract: The corrosion behaviour of irradiated MOX fuel (47 GWd/tHM) has been studied in an autoclave experiment simulating repository conditions. Fuel fragments were corroded at room temperature in a 10 mM NaCl/2 mM NaHCO3 solution in presence of dissolved H2 for 2100 days. The results show that dissolved H2 in concentration 1 mM and higher inhibits oxidation and dissolution of the fragments. Stable U and Pu concentrations were measured at 7 1010 and 5 1011 M, respectively. Caesium was only released during the first two years of the experiment. The results indicate that the UO2 matrix of a spent MOX fuel is the main contributor to the measured dissolution, while the corrosion of the high burn-up Pu-rich islands appears negligible.
JRC Institute:Institute for Transuranium Elements

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