Science and Technology of Nuclear Installations / 2012 / Article / Tab 1

Research Article

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
Thermal capture
Fast fission
Thermal fission
Fast neutron production
Thermal neutron production
Fast removal 2.063