Dissolution behavior of MgO based inert matrix fuel for the transmutation of minor actinides

摘要: Abstract This study explores the dissolution properties of magnesia-based inert matrix nuclear fuel (IMF) containing transuranium elements (TRU). Pure MgO pellets as well CeO2, surrogate for TRU oxides, and are considered model systems genuine magnesia based were fabricated. The aim this is to identify conditions at which material can be selectively dissolved during head-end reprocessing step, allowing a separation from actinides, whereas actinides remain undissolved. behavior was studied in macroscopic batch experiments function nitric acid concentration, medium volume, temperature, stirring velocity, pellet density (85, 90, 96, 99%TD). To mimic with various burn-ups here fabricated varied. soluble even under mild (RT, 2.5 mol/L HNO3). rates different concentrations rather similar, rate strongly dependent on temperature. Via microscopic approach, developed describe evolution surface area determine normalized rate. Moreover, CeO2 determined concentration During MgO/CeO2 dissolves completely, while (>99%) remains intends provide profound understanding chemical performance IMF fissile material. feasibility discussed.