The linear and Doppler feedback components of the regional contributions of the power reactivity decrement (PRD) and of the temperature coefficient of reactivity for a 900-MW(thermal) homogeneous U10Zr-fueled sodium-cooled reactor are calculated. The PRD components are separated into power- and power-to-flow-dependent parts. The values of PRD and temperature coefficient components are compared with corresponding quantities calculated for the Experimental Breeder Reactor II. The implications of these comparisons on inherent safety characteristics of metal-fueled sodium-cooled reactors are discussed.