Estimation of the composition of MA nitride fuel irradiated in ADS

Tsubata, Yasuhiro   ; Sugawara, Takanori  ; Hayashi, Hirokazu 

Compositions of minor actinide (MA) nitride fuel irradiated in accelerator driven system was estimated. In burnup calculation ADS3D program developed by JAEA was used. The compositions of the MA nitride fuel of the 1st cycle after irradiation (thermal power: 800 MW, irradiation period: 600 days, cooling time: 4 years) was compared with those before irradiation. Reduction rate of the minor actinides (MA; Np, Am, Cm) was 29 at.%, and that of actinides (MA, U, Pu) was 16 at.% at the central part of the inner region. Reduction rates were smaller at the bottom of the outer region (12 at.% for MA, 5 at.% for An). The compositions of fission products were 5.4 at.% at the central part of the inner region, 3.6 at.% at the bottom of the outer region. Estimation of the chemical forms of FP elements based on the calculation of the spent fuel composition is in progress.