Research Article
Resolution of the Generalized Eigenvalue Problem in the Neutron Diffusion Equation Discretized by the Finite Volume Method
Table 6
Biblis reactor cross sections.
| Material | (cm) | (cm) | (cm−1) | (cm−1) | (cm−1) | (cm−1) | (cm−1) |
| 1 | 1.4360 | 0.3635 | 0.0095042 | 0.0750580 | 0.017754 | 0.0058708 | 0.0960670 | 2 | 1.4366 | 0.3636 | 0.0096785 | 0.0784360 | 0.017621 | 0.0061908 | 0.1035800 | 3 | 1.3200 | 0.2772 | 0.0026562 | 0.0715960 | 0.023106 | 0.0 | 0.0 | 4 | 1.4389 | 0.3638 | 0.0103630 | 0.0914080 | 0.017101 | 0.0074527 | 0.1323600 | 5 | 1.4381 | 0.3665 | 0.0100030 | 0.0848280 | 0.017290 | 0.0061908 | 0.1035800 | 6 | 1.4385 | 0.3665 | 0.0101320 | 0.0873140 | 0.017192 | 0.0064285 | 0.1091100 | 7 | 1.4389 | 0.3679 | 0.0101650 | 0.0880240 | 0.017125 | 0.0061908 | 0.1035800 | 8 | 1.4393 | 0.3680 | 0.0102940 | 0.0905100 | 0.017027 | 0.0064285 | 0.1091100 |
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