Unstructured Grids and the Multigroup Neutron Diffusion Equation

Table 1

Macroscopic cross-sections (units are not stated in the original reference, but they are assumed to be in cm⁻¹ or cm as appropriate).

	𝐷1	𝐷2	Σ1→2	Σ𝑎1	Σ𝑎2	𝜈Σ𝑓2	Material
1	1.5	0.4	0.02	0.01	0.080	0.135	Fuel 1
2	1.5	0.4	0.02	0.01	0.085	0.135	Fuel 2
3	1.5	0.4	0.02	0.01	0.130	0.135	Fuel 2 + rod
4	2.0	0.3	0.04	0	0.010	0	Reflector