ICCSE 2019 Conference

Neutronic performances of Pbnat, Pbnat-Bi, Pb208 and Pb208-Bi as a coolant of Modified CANDLE reactor
Nina Widiawati1, Zaki Suud1, Dwi Irwanto1, Sidik Permana1, Naoyuki Takaki2, and Hiroshi Sekimoto3

1Nuclear and Biophysics Department, Institut Teknologi Bandung, Indonesia.
2Department of Nuclear Safety Engineering, Tokyo, Tokyo City University, Japan
3Emeritus professor, Tokyo, Tokyo Institute of Technology


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.

Keywords: Pbnat, Pbnat-Bi, Pb208, SRAC2006, Neutron economy, Coolant material, modified CANDLE.

Topic: Nuclear and Radiation Computation

Link: https://ifory.id/abstract-plain/cpqYKnj4ayu2

Web Format | Corresponding Author (Nina Widiawati)