Preliminary Design Study of Small Power 30-50 MWt Experiment Power Reactor based on High Temperature Pebble Bed Gas Cooled Reactor Technology

Abstract

Pebble Bed Reactor (PBR) is one of the most promising nuclear power plant. It has advantages in terms of high thermal efficiency, economic and its safety features. To build an experimental power reactor based on PBR technology, it is important to understand all the aspects related to the neutronic, thermal hydraulic and safety features of this reactor type. In the present study, a set of calculations have been performed to find characteristics of selected parameters of the PBR design that significantly contributed to the neutronic aspect, such as number of uranium enrichment, pebble fuel speed, fuel loading scheme and burnup. Calculation and analysis was performed for 30 MWt and 50 MWt power.