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Liquid metal cooled fast reactor is a reactor that included in the Generation IV reactor. Some liquid metal that has been used as fast reactor coolant are sodium (Na), Pb, and Pb-Bi. Based on several studies, Pb-based coolant shows better neutronic performance than Na. Currently, there are many studies related to the utilization of Pb208, which is one of the Pb stable isotopes as a coolant material. It is due to Pb208 has the lowest neutron absorption cross-section value among other stable Pb isotopes even compared to Pbnatural. Using pb208 isotope as a coolant can increase the k-eff value compared to natural Pb. In this research, a neutronic performance comparison between Pbnat and Pb208 coolant will be performed in a fast reactor with modified CANDLE burnup scheme. A reactor with a modified CANDLE burnup scheme could directly use natural uranium as fuel. The neutronic calculation performed using the SRAC2006 program. The utilization of liquid Pb208 as coolant can achieved the highest k-eff value among all coolant materials. Hence, the used of excellent coolant material in a reactor with a modified CANDLE burnup scheme is expected to has a superior neutron economy.