“…From safety perspectives, it is essential to have a thorough knowledge of the chemistry of the nuclear fuel-sodium coolant interaction as the two might come into contact in the event of a breach of the stainless steel cladding. (U, Pu) O 2 mixed oxide fuel is currently the preferred option for SFRs, and as such, the structural [1,2], thermodynamic [3][4][5][6][7][8], magnetic [9][10][11], and spectroscopic [12][13][14][15][16][17][18][19] properties of the Na-U-O and Na-Pu-O ternary compounds have been investigated in the past. The potential products of interaction are numerous: (Na 3 UO 4 , NaUO 3 , Na 2 UO 4 , Na 4 UO 5 ,Na 2 U 2 O 7 , Na 6 U 7 O 24 ) [20][21][22][23]1,24,25], and (Na 2 PuO 3 , Na 3 PuO 4 , Na 6 PuO 5 , Na 4 Pu 2 O 5 , Na 4 PuO 5 , Na 5 PuO 6 ) [1,2,26] for the first and second systems, respectively, but not all well characterized.…”