High-Conversion Th-U-233 Fuel Cycle for Current Generation in PWRs

Abstract

The main goal of this study is to evaluate the operational feasibility of the high conversion (HC) Th-U233 PWR core through performing the 3D fully coupled neutronic and thermal-hydraulic (T-H) analysis. The proposed HC core model consists of 193 typical 17×17 PWR fuel assemblies. Each fuel assembly is subdivided into two regions designated as seed and blanket. The central seed re-gion, which has high U233 content, serves as a neutron supplier for the peripheral blanket region. The blanket region consists mostly of Th232 and acts as a U233 breeder.