DISSOLUTION OF DIFFERENT TYPES OF NUCLEAR FUELS IN NITRIC ACID
The dissolution behavior of different types of so called advanced fuels (UC, (U,Pu)C, U(C,N), UN and (U,Pu)N) is compared to that of commonly used oxide fuels (UO2 and (U,Pu)O2). The influence of experimental parameters such as nitric acid molarity, dissolution temperature, fuel density and composition on the gas evolution is studied together with the composition of the resulting solution. Upon dissolution of nitrides in contrast to carbides and oxides, N2 is found in the offgas and ammonium ions are detected in the dissolver solution; between 10 and 19 percent of the UN nitrogen are transformed into NH4f5. Carbides and nitrides dissolve much faster than oxides and they do not leave any residue (unirradiated materials). Depending on the fuel composition and the dissolution parameters between 10 and 63 % of the carbon present in the fuel are oxidized to CO2.
Bibliographic Reference: INTERNATIONAL CONFERENCE ON NUCLEAR REPROCESSING AND WASTE MANAGEMENT, PARIS (FRANCE), AUG. 24-28, 1987 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 33451 ORA
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Record Number: 1989126000800 / Last updated on: 1988-02-01
Available languages: en