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Surface mediated processes in the interaction of spent fuel α-doped UO2 with H2

Daqing Cui ; Ella Ekeroth ; Patrik Fors (Institutionen för kemi- och bioteknik, Kärnkemi) ; Kastriot Spahiu (Institutionen för kemi- och bioteknik, Kärnkemi)
Materials Research Society Symposium Proceedings: Actinides 2008 - Basic Science, Applications and Technology; San Francisco, CA; United States; 25 March 2008 through 28 March 2008 (02729172). Vol. 1104 (2008), p. 87-99.
[Konferensbidrag, refereegranskat]

In most deep disposal concepts, large amounts of hydrogen are expected to be produced by the anoxic corrosion of massive iron containers. At repository temperatures, hydrogen is quite inert and is not expected to contribute to the redox capacity of the deep groundwaters. In several recent works, a large impact of dissolved hydrogen on the dissolution of the LWR or MOX fuel and UO 2(s) doped with 233U or 238Pu has been observed. For hydrogen concentrations above a certain limit, the dissolution rates of these highly radioactive materials drop to very low values. A discussion of the results obtained with spent fuel or ?-doped UO 2 in the presence of a range of hydrogen concentrations is presented. Typical for all measurements under such conditions are the very low long term concentrations of uranium and other redox-sensitive radionuclides, such as Tc and the minor actinides. The concentrations of U are systematically lower than the values measured during UO2(s) solubility measurements carried out in the presence of strong reducing agents. Measurements of the radiolytic oxygen after long leaching periods result in values below detection limit. The investigation of the surface of spent fuel or UO2(s) pellets doped with 233U by XPS after long periods of testing shows absence of oxidation. The kinetics of the release of non-redox sensitive elements such as Sr and Cs, used to estimate fuel matrix dissolution rates, is also discussed. An attempt is made to propose potential mechanisms responsible for the observed behaviour, based mainly on data from studies on the interaction of water adsorbed on the surfaces of metal oxides or actinide oxides with radiation. Another important effect observed in recent studies is the existence of a threshold for the specific alpha activity below which no measurable influence of the alpha radiolysis on the uranium release from UO2 is observed. The importance of such a threshold for the behaviour of spent fuel under repository conditions encompassing very long time scales will be discussed, as well as the necessity to better investigate the mechanisms of recombination reactions in a thin water layer on the surface of actinide oxides affected by ?- radiolysis.



Denna post skapades 2017-12-06.
CPL Pubid: 253588

 

Institutioner (Chalmers)

Institutionen för kemi- och bioteknik, Kärnkemi (2005-2014)

Ämnesområden

Kärnkemi

Chalmers infrastruktur