Leaching of 53MW/d kgU Spent Nuclear Fuel in a Flow-through Reactor
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.
SERRANO PURROY Daniel;
CLARENS Federic;
GLATZ Jean-Paul;
WEGEN Detlef;
CHRISTIANSEN Birgit;
DE PABLO J.;
GIMENEZ J.;
CASAS I.;
MARTINEZ-ESPARZA A.;
2010-01-25
OLDENBOURG VERLAG
JRC56815
0033-8230,
https://publications.jrc.ec.europa.eu/repository/handle/JRC56815,
10.1524/ract.2009.1640,
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