Resolution of the Generalized Eigenvalue Problem in the Neutron Diffusion Equation Discretized by the Finite Volume Method

Table 4

2D homogeneous reactor power errors (%) corresponding to the first eigenvalue.

Node	Structured mesh			Unstructured mesh
	10 cm	5 cm	2 cm	10 cm	5 cm	2 cm
1	0.009206	0.000081	0.000069	0.094629	0.131237	0.018789
2	0.005681	0.001217	0.000559	0.005927	0.002009	0.005058
3	0.002318	0.002675	0.001150	0.098431	0.136212	0.015750
4	0.010802	0.001601	0.000126	0.091223	0.125323	0.007585
5	0.014169	0.003062	0.000684	0.000774	0.005144	0.001788
6	0.017709	0.004348	0.001148	0.073893	0.111893	0.015444
7	0.009206	0.000081	0.000058	0.092636	0.096630	0.020416
8	0.005672	0.001208	0.000577	0.006823	0.000913	0.001457
9	0.002318	0.002686	0.001182	0.082769	0.141282	0.007689