Feedback components of a Pu-fueled compared to a U-fueled 900 MWt LMR

Abstract The feedback components of the regional contributions of the power reactivity decrement (PRD) and of the temperature coefficient of reactivity for a 900 MWt homogeneous UPu10Zr-fueled Na-cooled fast reactor are calculated. These PRD components are also separated into power dependent and power-to-flow dependent parts. The values of the PRD components and of the temperature coefficient components are compared with corresponding quantities of an analogous U10Zr-fueled reactor. The effects of these values upon quantities useful in the interpretations of inherent safety characteristics of metalfueled Na-cooled fast reactors are presented.