Computational Method for Global Sensitivity Analysis of Reactor Neutronic Parameters

Table 1

Assembly homogenized 2-group cross-sections [21].

Variable	Notation	Value, cm^−1
Fast capture	Σ^1𝑐	5.336⋅10^−3
Thermal capture	Σ^2𝑐	2.693⋅10^−2
Fast fission	Σ^1𝑓	1.9124⋅10^−3
Thermal fission	Σ^2𝑓	2.8438⋅10^−2
Fast neutron production	𝜈Σ^1𝑓	4.920⋅10^−3
Thermal neutron production	𝜈Σ^2𝑓	6.929⋅10^−2
Fast removal	Σ𝑠^1→2	2.063 ⋅10^−2