Research Article
Computational Method for Global Sensitivity Analysis of Reactor Neutronic Parameters
Table 1
Assembly homogenized 2-group cross-sections [
21].
| Variable | Notation | Value, cmā1 |
| Fast capture | | | Thermal capture | | | Fast fission | | | Thermal fission | | | Fast neutron production | | | Thermal neutron production | | | Fast removal | | 2.063 |
|
|