This is a standard nuclear engineering benchmark (IAEA number EIR-2) describing an external-force-driven configuration without fissile materials present, using one-group neutron diffusion approximation
(1)
The domain of interest is a 96 x 86 cm rectangle consisting of five regions:
The unknown is the neutron flux . The values of the diffusion coefficient , absorption cross-section and the source term are constant in the subdomains. The source in areas 1 and 3 and zero elsewhere. Boundary conditions for the flux are zero everywhere.
This example uses multiple weak forms that are associated with different material markers.
Solution:
Final mesh (h-FEM with linear elements):
Final mesh (h-FEM with quadratic elements):
Final mesh (hp-FEM):
DOF convergence graphs:
CPU time convergence graphs: