Analysis of the Neutronic characteristics of GFR-2400 fast reactor using MCNPX transport code

الملخص EN

The 2400 MW Gas Cooled Fast Reactor (GFR2400) is a promising potential candidate for future sustainable and economic nuclear power systems.

It is a highly innovative system with advanced geometrical design and fuel materials (Ceramic fuel pellets of mixed uranium‐plutonium carbide within fuel pins).

The active fuel region of this reactor is divided radially into two core zones of different fissile plutonium enrichments namely, inner core fuel assemblies (IC), and outer core fuel assemblies (OC).

Using MCNPX transport code, 3D heterogeneous model of GFR2400 core has been designed to study the neutronic characteristics of the GFR2400 concept and to simulate its operation during a fuel cycle of a duration 1443 effective full power days.

The obtained results show good agreement with previous studies and confirm the capability of the GFR2400 concept to achieve sustainability