Research Article

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

Table 13

Numbering of 3D homogeneous reactor nodes.

1st axial plane2nd axial plane3rd axial plane4th axial plane5th axial plane6th axial plane

7 8916 171825 262734 353643 444552 5354
4 5613 141522 232431 323340 414249 5051
1 2310 111219 202128 293037 383946 4748