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

Table 1

2D homogeneous reactor cross sections.

𝐷1 (cm)	𝐷2 (cm)	Σ𝑎1 (cm^−1)	Σ𝑎2 (cm^−1)	𝜐Σ𝑓1 (cm^−1)	𝜐Σ𝑓2 (cm^−1)	Σ12 (cm^−1)
1.28205128205	0.666667	0.01	0.1	0.01	0.109017634020268	0.075