Study on advanced LWR MOX fuel for effective Pu utilization and reduction of spent fuel assemblies

Naganuma, Masayuki  ; Ikusawa, Yoshihisa   ; Shuji, Yoshiyuki ; Suzuki, Kiichi  

As one of the studies for advancement of LWR MOX fuel, fuel concepts that can contribute to effective plutonium utilization and reduction of spent fuel assemblies in existing reactors were studied. To contribute to this purpose, candidate fuel concepts with the potential to increase the amount of Pu loading in the assembly for PWRs were devised within the current MOX fuel guidelines, and their characteristics were compared and evaluated. As a result, it was found that a fuel type with GdO-doped UO fuel pins installed at the assembly corners to adjust the power peaking in the assembly and the reactivity in the BOC is promising and the amount of Pu loading can be increased by approximately 15% compared to the current MOX fuel core. Under the condition that the amount of Pu used for MOX fuel per year is constant, the number of MOX fuel assemblies to be fabricated can be reduced by approximately 15%, therefore, the spent fuel can be also expected to be reduced by the same amount.