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|Title:||Corrosion of Irradiated MOX Fuel in Presence of Dissolved H2|
|Authors:||CARBOL Paul; FORS Patrick; VAN WINCKEL Stefaan; SPAHIU K.|
|Citation:||JOURNAL OF NUCLEAR MATERIALS vol. 392 no. 1 p. 45-54|
|Publisher:||ELSEVIER SCIENCE BV|
|Type:||Articles in periodicals and books|
|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:||Nuclear Safety and Security|
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