Nuclear and thermal analysis of MK-III core with high Pu contented fuel

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In this investigation, Pu fissile coefficients (reactivity ratio of nuclide) of MK-III core were calculated and Pu enrichment of three kinds of Pu composition were adjusted so that their reactivity worth are as much as ones of the fuel of MK-III standard core and the characteristics of MK-III cores with these fuels were evaluated. The contents of this calculation are as follows. (1)Calculation of Pu fissile coefficients. Normalizing coefficient of Pu as 1.0, Pu fissile coefficients (reactivity ratio of nuclide) of MK-III core were calculated about U, U, U, Pu, Pu, Pu, Pu and Am. The coefficients of U and Pu are 0.7 and 1.3. (2)Survey of fissile enrichment. Using Pu produced from spent LWR fuel of 60,70 and 80 GWd/t, as fuel of MK-III core, their enrichments of outer core fuel are about 32%, 34% and 36%. The higher Pu fraction of Pu is, the smaller burnup reactivity is. Maximum of reduction of burnup reactivity is 0.02% k/kk'. Using Pu produced from high burnup spent fuel, maximum linear heat rate is below 414 W/cm, maximum pin burnup is below 89,100 MWd/t. Power distribution and power peaking factor of these core are similar to ones of the MK-III standard core.