Search Results - "Eklund, U B"

Determination of dissolution rates of spent fuel in carbonate solutions under different redox conditions with a flow-through experiment by Röllin, S, Spahiu, K, Eklund, U.-B

“…Dissolution rates of spent UO 2 fuel have been investigated using flow-through experiments under oxidizing, anoxic and reducing conditions. For oxidizing…”
Get full text

Transport and leaching of technetium and uranium from spent UO2 fuel in compacted bentonite clay by RAMEBÄCK, H, ALBINSSON, Y, SKALBERG, M, EKLUND, U. B, KJELLBERG, L, WERME, L

Get full text

Determination of U(IV) and U(VI) by ion chromatography–inductively coupled plasma mass spectrometry and its application to kinetic studies by Röllin, Stefan, Eklund, Ulla-Britt

“…The ions normally formed by actinides in aqueous solutions by the oxidation states III–VI are M 3+, M 4+, MO 2 + and MO 2 2+, respectively. Oxidation state…”
Get full text

Transport and leaching of technetium and uranium from spent UO sub 2 fuel in compacted bentonite clay by Rameback, H, Albinsson, Y, Skalberg, M, Eklund, U B, Kjellberg, L, Werme, L

“…The transport properties of Tc and U in compacted bentonite clay and the leaching behaviour of these elements from spent nuclear fuel in the same system were…”
Get full text

Dissolution of irradiated fuel: a radiolytic mass balance study by Eriksen, Trygve E., Eklund, Ulla-Britt, Werme, Lars, Bruno, Jordi

“…We have studied the production of H 2,0 2 and H 20 2 by radiolysis of the leach solution in a closed system containing fragments of irradiated PWR fuel and…”
Get full text