Chemical potential of oxygen of UO2 close to stoichiometry

Oxygen stoichiometry shift of irradiated LWR-fuels at high burn-ups: Review of data and alternative interpretation of recently published results

“…2. Compilation of oxygen potential vs. oxygen to metal ratios data for the systems UO 2+x [29,[31][32][33][34], U 0.75 Pu 0.25 O 2Àx [30], simulated LWR-fuels (Burn-up = 5, 10 at.%) [29] and simulated MOXfuels (Pu = 0.25; burn-up = 5, 10 at.%) [30], according to thermogravimetric (TG) and galvanic-solid electrolyte (EMF) measurements from different sources, and thermodynamic calculations for the system U 0.6 Pu 0.4 O 2±x [1]. Comparison with oxygen potential measurements by the EMF-method of irradiated fuels in the burn-up range 28.9-100 GWd/tM [13][14][15].…”

Oxygen potentials of plutonium and uranium mixed oxide

“…In the range of near stoichiometric composition, the DG O 2 changes drastically with the change of the O/M ratio. There are a number of experimental data of the DG O 2 for UO 2 [5][6][7][8][9][10][11], which is the fuel in light water reactors (LWRs). On the other hand, data for MOX fuel which is used in fast reactors (FRs) [12][13][14][15][16][17][18][19][20][21][22][23] are limited.…”

Over forty years of ‘Thermodynamics of Nuclear Materials’

“…Blackburn justifies this from the better fits to experimental data with his assumptions. However, Baranov and Godin [41] chose U 3+ , U 4+ and U 5+ in a similar model.…”

“…[40]. Curve from model of Hyland [41]. X m is measured deviation from stoichiometric composition, UO 2 .…”

“…Potter / Journal of Nuclear Materials 389 (2009)[29][30][31][32][33][34][35][36][37][38][39][40][41][42][43][44] …”