The separation of fission products from irradiated UO
2 in fused nitrate systems was studied by the following procedure:
Dissolution of UO2 in fused NH
4NO
3; adsorption of fission products on glass powder; fused salt chromatography with γ-Al
2O
3; evaporation from fused nitrates; and precipitation of U-compound (probably alkali uranate, M
2U
2O
7) in a fused LiNO
3-KNO
3 mixture. Radiochemically pure Zr-Nb was selectively separated from the fused NH4NO3 melt by adsorption. Ru and I were completely evaporated from fused LiNO3-KNO3 mixture at above 280°C and from fused NH
4NO
3 at above 240°C, respectively. By means of chromatography with a γ-Al
2O
3 column, Zr-Nb and rare earths were completely separated from U in fused NH
4NO
3 or fused NH
4NO
3-LiNO
3 medium at 150°to 180°C, and further, Cs, Ba and Ru were also expected to be separable from U under suitable condition. When the U-compound was precipitated in fused LiNO
3-KNO
3 at 350°C, Cs, Sr, Ba and Ru were fairly well separated from U.
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