[2K06-10] Reactor and Safety Analysis

[2K06] Neutron diffusion theory with the IGA method

*Willem van Rooijen¹, Riho Horita² (1. Research Institute of Nuclear Engineering, University of Fukui, 2. Nuclear Power and Energy Safety Engineering Program, Graduate School of Engineering, University of Fukui)

Keywords:Diffusion theory, Finite Element Method, IGA method, Arbitrary geometry, Nuclear reactor core analysis

In earlier work we presented a method to solve the neutron transport equation on arbitrary geometry with the IGA method. In the current work this approach has been extended to neutron diffusion theory. Since the implementation of diffusion theory in the IGA method is different from transport theory, this presentation will focus on the theoretical details of implementing the IGA method for neutron diffusiont theory.