[3D01-05] Advanced Reactors Design

9:30 AM - 9:45 AM JST(12:30 AM - 12:45 AM UTC)

[3D01] Neutronics and Safety Evaluation of Directly Reusing Spent Fuel in a High-Temperature Gas-Cooled Reactor

*Hong Fatt Chong¹, Hiroshi Sagara¹ (1. Tokyo Tech)

Keywords:

direct reuse,high-temperature gas-cooled reactor,spent fuel,neutronics,safety,proliferation resistance,high burnup

A novel spent fuel direct reuse strategy concept for prismatic-block type high-temperature gas-cooled reactor (HTGR) has been proposed to achieve high burnup and high proliferation resistance. This research aims to evaluate the neutronics and safety properties of a direct reuse HTGR core layout, in which the irradiated driver fuel is being relocated to the newly expanded low power fuel region in the core for direct reuse with mass balance considerations.